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		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3955</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3955"/>
		<updated>2012-04-21T18:22:57Z</updated>

		<summary type="html">&lt;p&gt;Castro: &lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new Department of Economy and Competitiveness (MINECO)]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one Working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources.This experimental RAFM steel grade was obtained in a melting Pilot Plant by means of a High Vacuum induction melting furnace in order to assure a good control and to avoid possible impurities. The data obtained in the process of microstructural characterization (hardness or grain size), as in the mechanical tests put into practice at different temperatures as tensile test, facture test as well as the evaluation of a preliminary welding study, show a similar behavior to EUROFER 97-2.&lt;br /&gt;
. &amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|right|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
# [http://www.tecnofus-doculib.net TECNO_FUS DOCULIB website for the WG Members]&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3954</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3954"/>
		<updated>2012-04-21T18:19:59Z</updated>

		<summary type="html">&lt;p&gt;Castro: &lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one Working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources.This experimental RAFM steel grade was obtained in a melting Pilot Plant by means of a High Vacuum induction melting furnace in order to assure a good control and to avoid possible impurities. The data obtained in the process of microstructural characterization (hardness or grain size), as in the mechanical tests put into practice at different temperatures as tensile test, facture test as well as the evaluation of a preliminary welding study, show a similar behavior to EUROFER 97-2.&lt;br /&gt;
. &amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|right|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
# [http://www.tecnofus-doculib.net TECNO_FUS DOCULIB website for the WG]&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3870</id>
		<title>LNF:Organization</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3870"/>
		<updated>2012-01-18T19:53:27Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* TJ-II Operation */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;== Laboratorio Nacional de Fusión ==&lt;br /&gt;
&lt;br /&gt;
Asociación [[Euratom]]-[[CIEMAT]]: see [[Laboratorio Nacional de Fusión]].&lt;br /&gt;
&lt;br /&gt;
The telephone numbers listed below are extensions; to call from outside the laboratory,  dial: +34-91346xxxx,  where xxxx is the extension. (When using 4-digit dialing from inside the laboratory: substitute any initial &amp;quot;0&amp;quot; by a &amp;quot;7&amp;quot;.)&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sanz,  Joaquin,  Director  || 6387 &lt;br /&gt;
|-&lt;br /&gt;
| Aranda Nuñez,  Doralice || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Cabrero Rojo,  Francisco J. || -&lt;br /&gt;
|-&lt;br /&gt;
| Carbajo Josa,  Fernando A. || 6153&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Cubero,  Mª. Angeles || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Guerard Ortego,  Carlos Kjell || -&lt;br /&gt;
|-&lt;br /&gt;
| Marcón,  Gianpaolo || -&lt;br /&gt;
|-&lt;br /&gt;
| Wolfers,  Gilles || 6638&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Experimental division ===&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Hidalgo Vera,  Carlos,  Head Investigator  || 6498&lt;br /&gt;
|-&lt;br /&gt;
| Alonso de Pablo, Arturo || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Arevalo Gutierrez,  Juan || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Baciero Adrados,  Alfonso || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Baiao, Diana || 0917&lt;br /&gt;
|-&lt;br /&gt;
| Blanco Villareal,  Emilio J. || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Calderón Obaldia,  Eduardo || -&lt;br /&gt;
|-&lt;br /&gt;
| Carralero Ortiz,  Daniel || 7917&lt;br /&gt;
|-&lt;br /&gt;
| Carranza Arias,  José Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Esteban Hernández,  Luis || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Estrada García,  Mª. Teresa || 0845&lt;br /&gt;
|-&lt;br /&gt;
| Fontdecaba Climent,  Jose María || 6642&lt;br /&gt;
|-&lt;br /&gt;
| García Cortés,  Mª. Isabel || 6515&lt;br /&gt;
|-&lt;br /&gt;
| Happel,  Tim || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Hernanz Hernanz,  Francisco J. || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Herranz Marco,  Jesús Antonio || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Hollmann,  Eric || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Gómez,  Rubén Javier || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Rey,  David || 6578&lt;br /&gt;
|-&lt;br /&gt;
| McCarthy,  Kieran Joseph || 0846&lt;br /&gt;
|-&lt;br /&gt;
| Medina Yela,  Francisco || 0847&lt;br /&gt;
|-&lt;br /&gt;
| Morera Hidalgo,  Julio Andrés || -&lt;br /&gt;
|-&lt;br /&gt;
| Ochando Garcia,  Mª. Antonia || 6462&lt;br /&gt;
|-&lt;br /&gt;
| de Pablos Hernández,  Jose Luis || 6374&lt;br /&gt;
|-&lt;br /&gt;
| Pastor Díaz,  Ignacio || 6324&lt;br /&gt;
|-&lt;br /&gt;
| Pedrosa Luna,  Mª. Angeles || 6493&lt;br /&gt;
|-&lt;br /&gt;
| Rapisarda Socorro,  David || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Fernández,  Mª. Carmen || 6647&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Gómez,  Miguel || 6397&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Admin|van Milligen, Boudewijn]] || 6379&lt;br /&gt;
|-&lt;br /&gt;
| Zurro Hernández, Bernardo || 6457&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Operation ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ascasíbar,  Enrique,  Head Investigator  || 6369&lt;br /&gt;
|-&lt;br /&gt;
| Alegre Castro, Daniel || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Barrio Villalba, Felix || 6285&lt;br /&gt;
|-&lt;br /&gt;
| de la Cal Heusch, Eduardo || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Cappa Ascasíbar, Alvaro || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Castrejón Moreno, Javier || 6803&lt;br /&gt;
|-&lt;br /&gt;
| Castro Rojo, Rodrigo || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Catalán Moreno, Gregorio || 6643&lt;br /&gt;
|-&lt;br /&gt;
| Chamorro Lastra, Manuel || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Ferreira Somoza, José Antonio || 2579&lt;br /&gt;
|-&lt;br /&gt;
| García Gomez, Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| García Sánchez, Pablo || -&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Rivero, Guillermo ||&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Sanz, Sergio || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Guasp Pérez, Jose || 6510&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Denche, Andrés Enrique || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Liniers Vazquez, Macarena || 0844&lt;br /&gt;
|-&lt;br /&gt;
| López Razola, Justo || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Martín Diaz, Fernando || -&lt;br /&gt;
|-&lt;br /&gt;
| Martín Hernandez, Felix || 6824&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Fernandez, Jose || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Melón Blanco, Luis Jesús || 6285&lt;br /&gt;
|-&lt;br /&gt;
| Mirones Piulestan, Eloy || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Olivares Fernandez, Julian || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Pereira Gonzalez, Augusto || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Portas Ferreiro, Ana Belén || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Pretty, David || -&lt;br /&gt;
|-&lt;br /&gt;
| Redondo Redondo, Mariano || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Rios Marquez, Luis Maria || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rojo Lozano, Beatriz || 0916&lt;br /&gt;
|-&lt;br /&gt;
| Romero Gonzalez, Jesus Antonio || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Ros Vivancos, Alfonso || 6642  || Sala Control 6828;  || Lab. &amp;amp;mu;Ondas 6808&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sarabia, Emilio || 6762&lt;br /&gt;
|-&lt;br /&gt;
| Sebastian Alfaro, José Antonio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Tabarés Vazquez, Francisco Luis || 6458&lt;br /&gt;
|-&lt;br /&gt;
| Tafalla García, David || 0843&lt;br /&gt;
|-&lt;br /&gt;
| Tesfaye Girma, Wurgie || -&lt;br /&gt;
|-&lt;br /&gt;
| Tolkachev, Alexander || 6828&lt;br /&gt;
|-&lt;br /&gt;
| Vega Sánchez, Jesús Antonio || 6474&lt;br /&gt;
|-&lt;br /&gt;
| Velasco de la Cuadra, Gregorio || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Sala operación NBI  || 6851&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Fusion theory unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Castejón,  Francisco,  Head Investigator  || 6504&lt;br /&gt;
|-&lt;br /&gt;
| Barrera Orte,  Laura || 0917&lt;br /&gt;
|-&lt;br /&gt;
| de Bustos Molina,  Andrés || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Rubio,  Iván || 6739&lt;br /&gt;
|-&lt;br /&gt;
| García Regaña,  José Manuel || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Iglesias,  Antonio || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Aparicio,  Juan Antonio || 6503&lt;br /&gt;
|-&lt;br /&gt;
| López Bruna,  Daniel || 6638&lt;br /&gt;
|-&lt;br /&gt;
| López Fraguas,  Antonio || 0850&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Esolano|Rodríguez-Solano Ribeiro,  Emilia]]|| 6153&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez González,  Edilberto || 6162&lt;br /&gt;
|-&lt;br /&gt;
| Velasco Garasa,  José Luis || 6640&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Engineering unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Alonso,  José Javier,  Head Investigator  || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Álvarez Benitez,  Pio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Botija Pérez,  José || 6329&lt;br /&gt;
|-&lt;br /&gt;
| Carrasco García,  Ricardo || 7928&lt;br /&gt;
|-&lt;br /&gt;
| Kirpitchev,  Igor || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Lapayese Puebla,  Fernando || 0928&lt;br /&gt;
|-&lt;br /&gt;
| Medrano Casanova,  Mercedes || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Méndez Montero,  Purificación || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Pacios Rodríguez,  Luis || 6644&lt;br /&gt;
|-&lt;br /&gt;
| de la Peña Gómez,  Ángel || 6644&lt;br /&gt;
|-&lt;br /&gt;
| Pérez Pichel,  Germán || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Queral Mas,  Vicente || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Rivero,  Francisco || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rincón Rincón,  María Esther || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Soleto Palomo,  M. Alfonso || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Weber Suárez,  Moisés || 6636&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Technology division ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ibarra Sánchez,   Ángel,  Head Investigator  || 6507&lt;br /&gt;
|-&lt;br /&gt;
| Hodgson Hampson,  Eric Richard || 6202&lt;br /&gt;
|-&lt;br /&gt;
| Arroyo Macias,   José Manuel || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Brañas Lasala,   Beatriz || 6289&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Pinto,   Julio || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carella,   Elisabetta || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carmona Torres,   José Miguel || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Casal Iglesias,   Natalia || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera, Paloma || 0852 ||7852&lt;br /&gt;
|-&lt;br /&gt;
| Cuarental García,   Irene || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Delgado Bueno,   Diego || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Berceruelo,   Iván || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Paredes,   Mª. Pilar || 2581&lt;br /&gt;
|-&lt;br /&gt;
| García Gonzalez,   Juan Manuel || 6578&lt;br /&gt;
|-&lt;br /&gt;
| García Sanz,   Ángela || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Gómez-Ferrer Herran,   Begoña || 2574 || Lab. 6512&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez López,   Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Viada,   María || 2582&lt;br /&gt;
|-&lt;br /&gt;
| Hernandez Diaz,   Mª. Teresa || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Baena,   Francisco M. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| León Pichel,   Mónica || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Malo Huerta,   Marta || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Manzano Santamaria,   Javier || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Martín Laso,   Montserrat || 6512&lt;br /&gt;
|-&lt;br /&gt;
| Martín Martinez,   Mª. Piedad || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Alcalde,   Pablo Miguel || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Martinez-Albertos Bofarull,   José Luis || -&lt;br /&gt;
|-&lt;br /&gt;
| Molla Lorente,   Joaquín || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Moroño Guadalajara,   Alejandro A. || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Mota García,   Fernando || 6578&lt;br /&gt;
|-&lt;br /&gt;
| Ortíz,   Christophe || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Oyarzabal Vicente,   Eider || -&lt;br /&gt;
|-&lt;br /&gt;
| Palermo,   Iole || 6784&lt;br /&gt;
|-&lt;br /&gt;
| Parro Albeniz,   Marcos || 0916 || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Pérez López,   Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Gallardo,   Angel || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Regidor Serrano,   David || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Salvador,   Diego || 6613&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Sánchez,   Mª. Teresa || 6203&lt;br /&gt;
|-&lt;br /&gt;
| Sedano Miguel,   Luis Ángel || 0913 || 7913&lt;br /&gt;
|-&lt;br /&gt;
| Valle Paisan,   Francisco J. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Veredas Luque,   Gerardo || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Vila Vazquez,   Rafael Alberto || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Villa Ramos,   Daniel || 2579&lt;br /&gt;
|-&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Support unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Dabbah Ainstein, Dina || 7851&lt;br /&gt;
|-&lt;br /&gt;
| Moreno García, Sabina || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Romero Romero, Eulalia || 6161&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Rubio, Cristina || 6738&lt;br /&gt;
|-&lt;br /&gt;
| Torras Barneto, Mª Dolores || 6663&lt;br /&gt;
|}&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3869</id>
		<title>LNF:Organization</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3869"/>
		<updated>2012-01-18T19:49:13Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Laboratorio Nacional de Fusión */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;== Laboratorio Nacional de Fusión ==&lt;br /&gt;
&lt;br /&gt;
Asociación [[Euratom]]-[[CIEMAT]]: see [[Laboratorio Nacional de Fusión]].&lt;br /&gt;
&lt;br /&gt;
The telephone numbers listed below are extensions; to call from outside the laboratory,  dial: +34-91346xxxx,  where xxxx is the extension. (When using 4-digit dialing from inside the laboratory: substitute any initial &amp;quot;0&amp;quot; by a &amp;quot;7&amp;quot;.)&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sanz,  Joaquin,  Director  || 6387 &lt;br /&gt;
|-&lt;br /&gt;
| Aranda Nuñez,  Doralice || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Cabrero Rojo,  Francisco J. || -&lt;br /&gt;
|-&lt;br /&gt;
| Carbajo Josa,  Fernando A. || 6153&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Cubero,  Mª. Angeles || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Guerard Ortego,  Carlos Kjell || -&lt;br /&gt;
|-&lt;br /&gt;
| Marcón,  Gianpaolo || -&lt;br /&gt;
|-&lt;br /&gt;
| Wolfers,  Gilles || 6638&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Experimental division ===&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Hidalgo Vera,  Carlos,  Head Investigator  || 6498&lt;br /&gt;
|-&lt;br /&gt;
| Alonso de Pablo, Arturo || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Arevalo Gutierrez,  Juan || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Baciero Adrados,  Alfonso || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Baiao, Diana || 0917&lt;br /&gt;
|-&lt;br /&gt;
| Blanco Villareal,  Emilio J. || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Calderón Obaldia,  Eduardo || -&lt;br /&gt;
|-&lt;br /&gt;
| Carralero Ortiz,  Daniel || 7917&lt;br /&gt;
|-&lt;br /&gt;
| Carranza Arias,  José Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Esteban Hernández,  Luis || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Estrada García,  Mª. Teresa || 0845&lt;br /&gt;
|-&lt;br /&gt;
| Fontdecaba Climent,  Jose María || 6642&lt;br /&gt;
|-&lt;br /&gt;
| García Cortés,  Mª. Isabel || 6515&lt;br /&gt;
|-&lt;br /&gt;
| Happel,  Tim || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Hernanz Hernanz,  Francisco J. || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Herranz Marco,  Jesús Antonio || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Hollmann,  Eric || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Gómez,  Rubén Javier || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Rey,  David || 6578&lt;br /&gt;
|-&lt;br /&gt;
| McCarthy,  Kieran Joseph || 0846&lt;br /&gt;
|-&lt;br /&gt;
| Medina Yela,  Francisco || 0847&lt;br /&gt;
|-&lt;br /&gt;
| Morera Hidalgo,  Julio Andrés || -&lt;br /&gt;
|-&lt;br /&gt;
| Ochando Garcia,  Mª. Antonia || 6462&lt;br /&gt;
|-&lt;br /&gt;
| de Pablos Hernández,  Jose Luis || 6374&lt;br /&gt;
|-&lt;br /&gt;
| Pastor Díaz,  Ignacio || 6324&lt;br /&gt;
|-&lt;br /&gt;
| Pedrosa Luna,  Mª. Angeles || 6493&lt;br /&gt;
|-&lt;br /&gt;
| Rapisarda Socorro,  David || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Fernández,  Mª. Carmen || 6647&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Gómez,  Miguel || 6397&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Admin|van Milligen, Boudewijn]] || 6379&lt;br /&gt;
|-&lt;br /&gt;
| Zurro Hernández, Bernardo || 6457&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Operation ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ascasíbar,  Enrique,  Head Investigator  || 6369&lt;br /&gt;
|-&lt;br /&gt;
| Alegre Castro, Daniel || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Barrio Villalba, Felix || 6285&lt;br /&gt;
|-&lt;br /&gt;
| de la Cal Heusch, Eduardo || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Cappa Ascasíbar, Alvaro || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Castrejón Moreno, Javier || 6803&lt;br /&gt;
|&lt;br /&gt;
| Castro Rojo, Rodrigo || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Catalán Moreno, Gregorio || 6643&lt;br /&gt;
|-&lt;br /&gt;
| Chamorro Lastra, Manuel || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Ferreira Somoza, José Antonio || 2579&lt;br /&gt;
|-&lt;br /&gt;
| García Gomez, Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| García Sánchez, Pablo || -&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Rivero, Guillermo ||&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Sanz, Sergio || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Guasp Pérez, Jose || 6510&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Denche, Andrés Enrique || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Liniers Vazquez, Macarena || 0844&lt;br /&gt;
|-&lt;br /&gt;
| López Razola, Justo || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Martín Diaz, Fernando || -&lt;br /&gt;
|-&lt;br /&gt;
| Martín Hernandez, Felix || 6824&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Fernandez, Jose || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Melón Blanco, Luis Jesús || 6285&lt;br /&gt;
|-&lt;br /&gt;
| Mirones Piulestan, Eloy || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Olivares Fernandez, Julian || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Pereira Gonzalez, Augusto || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Portas Ferreiro, Ana Belén || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Pretty, David || -&lt;br /&gt;
|-&lt;br /&gt;
| Redondo Redondo, Mariano || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Rios Marquez, Luis Maria || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rojo Lozano, Beatriz || 0916&lt;br /&gt;
|-&lt;br /&gt;
| Romero Gonzalez, Jesus Antonio || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Ros Vivancos, Alfonso || 6642  || Sala Control 6828;  || Lab. &amp;amp;mu;Ondas 6808&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sarabia, Emilio || 6762&lt;br /&gt;
|-&lt;br /&gt;
| Sebastian Alfaro, José Antonio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Tabarés Vazquez, Francisco Luis || 6458&lt;br /&gt;
|-&lt;br /&gt;
| Tafalla García, David || 0843&lt;br /&gt;
|-&lt;br /&gt;
| Tesfaye Girma, Wurgie || -&lt;br /&gt;
|-&lt;br /&gt;
| Tolkachev, Alexander || 6828&lt;br /&gt;
|-&lt;br /&gt;
| Vega Sánchez, Jesús Antonio || 6474&lt;br /&gt;
|-&lt;br /&gt;
| Velasco de la Cuadra, Gregorio || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Sala operación NBI  || 6851&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Fusion theory unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Castejón,  Francisco,  Head Investigator  || 6504&lt;br /&gt;
|-&lt;br /&gt;
| Barrera Orte,  Laura || 0917&lt;br /&gt;
|-&lt;br /&gt;
| de Bustos Molina,  Andrés || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Rubio,  Iván || 6739&lt;br /&gt;
|-&lt;br /&gt;
| García Regaña,  José Manuel || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Iglesias,  Antonio || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Aparicio,  Juan Antonio || 6503&lt;br /&gt;
|-&lt;br /&gt;
| López Bruna,  Daniel || 6638&lt;br /&gt;
|-&lt;br /&gt;
| López Fraguas,  Antonio || 0850&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Esolano|Rodríguez-Solano Ribeiro,  Emilia]]|| 6153&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez González,  Edilberto || 6162&lt;br /&gt;
|-&lt;br /&gt;
| Velasco Garasa,  José Luis || 6640&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Engineering unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Alonso,  José Javier,  Head Investigator  || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Álvarez Benitez,  Pio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Botija Pérez,  José || 6329&lt;br /&gt;
|-&lt;br /&gt;
| Carrasco García,  Ricardo || 7928&lt;br /&gt;
|-&lt;br /&gt;
| Kirpitchev,  Igor || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Lapayese Puebla,  Fernando || 0928&lt;br /&gt;
|-&lt;br /&gt;
| Medrano Casanova,  Mercedes || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Méndez Montero,  Purificación || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Pacios Rodríguez,  Luis || 6644&lt;br /&gt;
|-&lt;br /&gt;
| de la Peña Gómez,  Ángel || 6644&lt;br /&gt;
|-&lt;br /&gt;
| Pérez Pichel,  Germán || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Queral Mas,  Vicente || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Rivero,  Francisco || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rincón Rincón,  María Esther || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Soleto Palomo,  M. Alfonso || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Weber Suárez,  Moisés || 6636&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Technology division ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ibarra Sánchez,   Ángel,  Head Investigator  || 6507&lt;br /&gt;
|-&lt;br /&gt;
| Hodgson Hampson,  Eric Richard || 6202&lt;br /&gt;
|-&lt;br /&gt;
| Arroyo Macias,   José Manuel || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Brañas Lasala,   Beatriz || 6289&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Pinto,   Julio || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carella,   Elisabetta || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carmona Torres,   José Miguel || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Casal Iglesias,   Natalia || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera, Paloma || 0852 ||7852&lt;br /&gt;
|-&lt;br /&gt;
| Cuarental García,   Irene || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Delgado Bueno,   Diego || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Berceruelo,   Iván || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Paredes,   Mª. Pilar || 2581&lt;br /&gt;
|-&lt;br /&gt;
| García Gonzalez,   Juan Manuel || 6578&lt;br /&gt;
|-&lt;br /&gt;
| García Sanz,   Ángela || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Gómez-Ferrer Herran,   Begoña || 2574 || Lab. 6512&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez López,   Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Viada,   María || 2582&lt;br /&gt;
|-&lt;br /&gt;
| Hernandez Diaz,   Mª. Teresa || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Baena,   Francisco M. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| León Pichel,   Mónica || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Malo Huerta,   Marta || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Manzano Santamaria,   Javier || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Martín Laso,   Montserrat || 6512&lt;br /&gt;
|-&lt;br /&gt;
| Martín Martinez,   Mª. Piedad || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Alcalde,   Pablo Miguel || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Martinez-Albertos Bofarull,   José Luis || -&lt;br /&gt;
|-&lt;br /&gt;
| Molla Lorente,   Joaquín || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Moroño Guadalajara,   Alejandro A. || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Mota García,   Fernando || 6578&lt;br /&gt;
|-&lt;br /&gt;
| Ortíz,   Christophe || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Oyarzabal Vicente,   Eider || -&lt;br /&gt;
|-&lt;br /&gt;
| Palermo,   Iole || 6784&lt;br /&gt;
|-&lt;br /&gt;
| Parro Albeniz,   Marcos || 0916 || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Pérez López,   Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Gallardo,   Angel || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Regidor Serrano,   David || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Salvador,   Diego || 6613&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Sánchez,   Mª. Teresa || 6203&lt;br /&gt;
|-&lt;br /&gt;
| Sedano Miguel,   Luis Ángel || 0913 || 7913&lt;br /&gt;
|-&lt;br /&gt;
| Valle Paisan,   Francisco J. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Veredas Luque,   Gerardo || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Vila Vazquez,   Rafael Alberto || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Villa Ramos,   Daniel || 2579&lt;br /&gt;
|-&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Support unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Dabbah Ainstein, Dina || 7851&lt;br /&gt;
|-&lt;br /&gt;
| Moreno García, Sabina || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Romero Romero, Eulalia || 6161&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Rubio, Cristina || 6738&lt;br /&gt;
|-&lt;br /&gt;
| Torras Barneto, Mª Dolores || 6663&lt;br /&gt;
|}&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3868</id>
		<title>LNF:Organization</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3868"/>
		<updated>2012-01-18T19:36:21Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Technology division */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;== Laboratorio Nacional de Fusión ==&lt;br /&gt;
&lt;br /&gt;
Asociación [[Euratom]]-[[CIEMAT]]: see [[Laboratorio Nacional de Fusión]].&lt;br /&gt;
&lt;br /&gt;
The telephone numbers listed below are extensions; to call from outside the laboratory,  dial: +34-91346xxxx,  where xxxx is the extension. (When using 4-digit dialing from inside the laboratory: substitute any initial &amp;quot;0&amp;quot; by a &amp;quot;7&amp;quot;.)&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sanz,  Joaquin,  Director  || 6387 &lt;br /&gt;
|-&lt;br /&gt;
| Aranda Nuñez,  Doralice || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Cabrero Rojo,  Francisco J. || -&lt;br /&gt;
|-&lt;br /&gt;
| Carbajo Josa,  Fernando A. || 6153&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera,  Paloma || 0852&lt;br /&gt;
|-&lt;br /&gt;
| Castro Rojo,  Rodrigo || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Cubero,  Mª. Angeles || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Guerard Ortego,  Carlos Kjell || -&lt;br /&gt;
|-&lt;br /&gt;
| Marcón,  Gianpaolo || -&lt;br /&gt;
|-&lt;br /&gt;
| Wolfers,  Gilles || 6638&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Experimental division ===&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Hidalgo Vera,  Carlos,  Head Investigator  || 6498&lt;br /&gt;
|-&lt;br /&gt;
| Alonso de Pablo, Arturo || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Arevalo Gutierrez,  Juan || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Baciero Adrados,  Alfonso || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Baiao, Diana || 0917&lt;br /&gt;
|-&lt;br /&gt;
| Blanco Villareal,  Emilio J. || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Calderón Obaldia,  Eduardo || -&lt;br /&gt;
|-&lt;br /&gt;
| Carralero Ortiz,  Daniel || 7917&lt;br /&gt;
|-&lt;br /&gt;
| Carranza Arias,  José Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Esteban Hernández,  Luis || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Estrada García,  Mª. Teresa || 0845&lt;br /&gt;
|-&lt;br /&gt;
| Fontdecaba Climent,  Jose María || 6642&lt;br /&gt;
|-&lt;br /&gt;
| García Cortés,  Mª. Isabel || 6515&lt;br /&gt;
|-&lt;br /&gt;
| Happel,  Tim || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Hernanz Hernanz,  Francisco J. || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Herranz Marco,  Jesús Antonio || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Hollmann,  Eric || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Gómez,  Rubén Javier || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Rey,  David || 6578&lt;br /&gt;
|-&lt;br /&gt;
| McCarthy,  Kieran Joseph || 0846&lt;br /&gt;
|-&lt;br /&gt;
| Medina Yela,  Francisco || 0847&lt;br /&gt;
|-&lt;br /&gt;
| Morera Hidalgo,  Julio Andrés || -&lt;br /&gt;
|-&lt;br /&gt;
| Ochando Garcia,  Mª. Antonia || 6462&lt;br /&gt;
|-&lt;br /&gt;
| de Pablos Hernández,  Jose Luis || 6374&lt;br /&gt;
|-&lt;br /&gt;
| Pastor Díaz,  Ignacio || 6324&lt;br /&gt;
|-&lt;br /&gt;
| Pedrosa Luna,  Mª. Angeles || 6493&lt;br /&gt;
|-&lt;br /&gt;
| Rapisarda Socorro,  David || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Fernández,  Mª. Carmen || 6647&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Gómez,  Miguel || 6397&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Admin|van Milligen, Boudewijn]] || 6379&lt;br /&gt;
|-&lt;br /&gt;
| Zurro Hernández, Bernardo || 6457&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Operation ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ascasíbar,  Enrique,  Head Investigator  || 6369&lt;br /&gt;
|-&lt;br /&gt;
| Alegre Castro, Daniel || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Barrio Villalba, Felix || 6285&lt;br /&gt;
|-&lt;br /&gt;
| de la Cal Heusch, Eduardo || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Cappa Ascasíbar, Alvaro || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Castrejón Moreno, Javier || 6803&lt;br /&gt;
|-&lt;br /&gt;
| Catalán Moreno, Gregorio || 6643&lt;br /&gt;
|-&lt;br /&gt;
| Chamorro Lastra, Manuel || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Ferreira Somoza, José Antonio || 2579&lt;br /&gt;
|-&lt;br /&gt;
| García Gomez, Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| García Sánchez, Pablo || -&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Rivero, Guillermo ||&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Sanz, Sergio || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Guasp Pérez, Jose || 6510&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Denche, Andrés Enrique || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Liniers Vazquez, Macarena || 0844&lt;br /&gt;
|-&lt;br /&gt;
| López Razola, Justo || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Martín Diaz, Fernando || -&lt;br /&gt;
|-&lt;br /&gt;
| Martín Hernandez, Felix || 6824&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Fernandez, Jose || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Melón Blanco, Luis Jesús || 6285&lt;br /&gt;
|-&lt;br /&gt;
| Mirones Piulestan, Eloy || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Olivares Fernandez, Julian || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Pereira Gonzalez, Augusto || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Portas Ferreiro, Ana Belén || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Pretty, David || -&lt;br /&gt;
|-&lt;br /&gt;
| Ratta Gutierrez, Giuseppe A. || 7918&lt;br /&gt;
|-&lt;br /&gt;
| Redondo Redondo, Mariano || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Rios Marquez, Luis Maria || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rojo Lozano, Beatriz || 0916&lt;br /&gt;
|-&lt;br /&gt;
| Romero Gonzalez, Jesus Antonio || 0852&lt;br /&gt;
|-&lt;br /&gt;
| Ros Vivancos, Alfonso || 6642  || Sala Control 6828;  || Lab. &amp;amp;mu;Ondas 6808&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sarabia, Emilio || 6762&lt;br /&gt;
|-&lt;br /&gt;
| Sebastian Alfaro, José Antonio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Tabarés Vazquez, Francisco Luis || 6458&lt;br /&gt;
|-&lt;br /&gt;
| Tafalla García, David || 0843&lt;br /&gt;
|-&lt;br /&gt;
| Tesfaye Girma, Wurgie || -&lt;br /&gt;
|-&lt;br /&gt;
| Tolkachev, Alexander || 6828&lt;br /&gt;
|-&lt;br /&gt;
| Vega Sánchez, Jesús Antonio || 6474&lt;br /&gt;
|-&lt;br /&gt;
| Velasco de la Cuadra, Gregorio || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Sala operación NBI  || 6851&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Fusion theory unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Castejón,  Francisco,  Head Investigator  || 6504&lt;br /&gt;
|-&lt;br /&gt;
| Barrera Orte,  Laura || 0917&lt;br /&gt;
|-&lt;br /&gt;
| de Bustos Molina,  Andrés || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Rubio,  Iván || 6739&lt;br /&gt;
|-&lt;br /&gt;
| García Regaña,  José Manuel || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Iglesias,  Antonio || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Aparicio,  Juan Antonio || 6503&lt;br /&gt;
|-&lt;br /&gt;
| López Bruna,  Daniel || 6638&lt;br /&gt;
|-&lt;br /&gt;
| López Fraguas,  Antonio || 0850&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Esolano|Rodríguez-Solano Ribeiro,  Emilia]]|| 6153&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez González,  Edilberto || 6162&lt;br /&gt;
|-&lt;br /&gt;
| Velasco Garasa,  José Luis || 6640&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Engineering unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Alonso,  José Javier,  Head Investigator  || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Álvarez Benitez,  Pio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Botija Pérez,  José || 6329&lt;br /&gt;
|-&lt;br /&gt;
| Carrasco García,  Ricardo || 7928&lt;br /&gt;
|-&lt;br /&gt;
| Kirpitchev,  Igor || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Lapayese Puebla,  Fernando || 0928&lt;br /&gt;
|-&lt;br /&gt;
| Medrano Casanova,  Mercedes || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Méndez Montero,  Purificación || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Pacios Rodríguez,  Luis || 6644&lt;br /&gt;
|-&lt;br /&gt;
| de la Peña Gómez,  Ángel || 6644&lt;br /&gt;
|-&lt;br /&gt;
| Pérez Pichel,  Germán || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Queral Mas,  Vicente || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Rivero,  Francisco || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rincón Rincón,  María Esther || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Soleto Palomo,  M. Alfonso || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Weber Suárez,  Moisés || 6636&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Technology division ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ibarra Sánchez,   Ángel,  Head Investigator  || 6507&lt;br /&gt;
|-&lt;br /&gt;
| Hodgson Hampson,  Eric Richard || 6202&lt;br /&gt;
|-&lt;br /&gt;
| Arroyo Macias,   José Manuel || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Brañas Lasala,   Beatriz || 6289&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Pinto,   Julio || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carella,   Elisabetta || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carmona Torres,   José Miguel || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Casal Iglesias,   Natalia || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera, Paloma || 0852 ||7852&lt;br /&gt;
|-&lt;br /&gt;
| Cuarental García,   Irene || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Delgado Bueno,   Diego || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Berceruelo,   Iván || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Paredes,   Mª. Pilar || 2581&lt;br /&gt;
|-&lt;br /&gt;
| García Gonzalez,   Juan Manuel || 6578&lt;br /&gt;
|-&lt;br /&gt;
| García Sanz,   Ángela || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Gómez-Ferrer Herran,   Begoña || 2574 || Lab. 6512&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez López,   Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Viada,   María || 2582&lt;br /&gt;
|-&lt;br /&gt;
| Hernandez Diaz,   Mª. Teresa || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Baena,   Francisco M. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| León Pichel,   Mónica || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Malo Huerta,   Marta || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Manzano Santamaria,   Javier || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Martín Laso,   Montserrat || 6512&lt;br /&gt;
|-&lt;br /&gt;
| Martín Martinez,   Mª. Piedad || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Alcalde,   Pablo Miguel || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Martinez-Albertos Bofarull,   José Luis || -&lt;br /&gt;
|-&lt;br /&gt;
| Molla Lorente,   Joaquín || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Moroño Guadalajara,   Alejandro A. || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Mota García,   Fernando || 6578&lt;br /&gt;
|-&lt;br /&gt;
| Ortíz,   Christophe || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Oyarzabal Vicente,   Eider || -&lt;br /&gt;
|-&lt;br /&gt;
| Palermo,   Iole || 6784&lt;br /&gt;
|-&lt;br /&gt;
| Parro Albeniz,   Marcos || 0916 || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Pérez López,   Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Gallardo,   Angel || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Regidor Serrano,   David || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Salvador,   Diego || 6613&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Sánchez,   Mª. Teresa || 6203&lt;br /&gt;
|-&lt;br /&gt;
| Sedano Miguel,   Luis Ángel || 0913 || 7913&lt;br /&gt;
|-&lt;br /&gt;
| Valle Paisan,   Francisco J. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Veredas Luque,   Gerardo || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Vila Vazquez,   Rafael Alberto || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Villa Ramos,   Daniel || 2579&lt;br /&gt;
|-&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Support unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Dabbah Ainstein, Dina || 7851&lt;br /&gt;
|-&lt;br /&gt;
| Moreno García, Sabina || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Romero Romero, Eulalia || 6161&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Rubio, Cristina || 6738&lt;br /&gt;
|-&lt;br /&gt;
| Torras Barneto, Mª Dolores || 6663&lt;br /&gt;
|}&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3867</id>
		<title>LNF:Organization</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Organization&amp;diff=3867"/>
		<updated>2012-01-18T19:31:15Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Technology division */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;== Laboratorio Nacional de Fusión ==&lt;br /&gt;
&lt;br /&gt;
Asociación [[Euratom]]-[[CIEMAT]]: see [[Laboratorio Nacional de Fusión]].&lt;br /&gt;
&lt;br /&gt;
The telephone numbers listed below are extensions; to call from outside the laboratory,  dial: +34-91346xxxx,  where xxxx is the extension. (When using 4-digit dialing from inside the laboratory: substitute any initial &amp;quot;0&amp;quot; by a &amp;quot;7&amp;quot;.)&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sanz,  Joaquin,  Director  || 6387 &lt;br /&gt;
|-&lt;br /&gt;
| Aranda Nuñez,  Doralice || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Cabrero Rojo,  Francisco J. || -&lt;br /&gt;
|-&lt;br /&gt;
| Carbajo Josa,  Fernando A. || 6153&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera,  Paloma || 0852&lt;br /&gt;
|-&lt;br /&gt;
| Castro Rojo,  Rodrigo || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Cubero,  Mª. Angeles || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Guerard Ortego,  Carlos Kjell || -&lt;br /&gt;
|-&lt;br /&gt;
| Marcón,  Gianpaolo || -&lt;br /&gt;
|-&lt;br /&gt;
| Wolfers,  Gilles || 6638&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Experimental division ===&lt;br /&gt;
&lt;br /&gt;
{|&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Hidalgo Vera,  Carlos,  Head Investigator  || 6498&lt;br /&gt;
|-&lt;br /&gt;
| Alonso de Pablo, Arturo || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Arevalo Gutierrez,  Juan || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Baciero Adrados,  Alfonso || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Baiao, Diana || 0917&lt;br /&gt;
|-&lt;br /&gt;
| Blanco Villareal,  Emilio J. || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Calderón Obaldia,  Eduardo || -&lt;br /&gt;
|-&lt;br /&gt;
| Carralero Ortiz,  Daniel || 7917&lt;br /&gt;
|-&lt;br /&gt;
| Carranza Arias,  José Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Esteban Hernández,  Luis || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Estrada García,  Mª. Teresa || 0845&lt;br /&gt;
|-&lt;br /&gt;
| Fontdecaba Climent,  Jose María || 6642&lt;br /&gt;
|-&lt;br /&gt;
| García Cortés,  Mª. Isabel || 6515&lt;br /&gt;
|-&lt;br /&gt;
| Happel,  Tim || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Hernanz Hernanz,  Francisco J. || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Herranz Marco,  Jesús Antonio || 0848&lt;br /&gt;
|-&lt;br /&gt;
| Hollmann,  Eric || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Gómez,  Rubén Javier || -&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Rey,  David || 6578&lt;br /&gt;
|-&lt;br /&gt;
| McCarthy,  Kieran Joseph || 0846&lt;br /&gt;
|-&lt;br /&gt;
| Medina Yela,  Francisco || 0847&lt;br /&gt;
|-&lt;br /&gt;
| Morera Hidalgo,  Julio Andrés || -&lt;br /&gt;
|-&lt;br /&gt;
| Ochando Garcia,  Mª. Antonia || 6462&lt;br /&gt;
|-&lt;br /&gt;
| de Pablos Hernández,  Jose Luis || 6374&lt;br /&gt;
|-&lt;br /&gt;
| Pastor Díaz,  Ignacio || 6324&lt;br /&gt;
|-&lt;br /&gt;
| Pedrosa Luna,  Mª. Angeles || 6493&lt;br /&gt;
|-&lt;br /&gt;
| Rapisarda Socorro,  David || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Fernández,  Mª. Carmen || 6647&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Gómez,  Miguel || 6397&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Admin|van Milligen, Boudewijn]] || 6379&lt;br /&gt;
|-&lt;br /&gt;
| Zurro Hernández, Bernardo || 6457&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== TJ-II Operation ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ascasíbar,  Enrique,  Head Investigator  || 6369&lt;br /&gt;
|-&lt;br /&gt;
| Alegre Castro, Daniel || 0914&lt;br /&gt;
|-&lt;br /&gt;
| Barrio Villalba, Felix || 6285&lt;br /&gt;
|-&lt;br /&gt;
| de la Cal Heusch, Eduardo || 6317&lt;br /&gt;
|-&lt;br /&gt;
| Cappa Ascasíbar, Alvaro || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Castrejón Moreno, Javier || 6803&lt;br /&gt;
|-&lt;br /&gt;
| Catalán Moreno, Gregorio || 6643&lt;br /&gt;
|-&lt;br /&gt;
| Chamorro Lastra, Manuel || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Ferreira Somoza, José Antonio || 2579&lt;br /&gt;
|-&lt;br /&gt;
| García Gomez, Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| García Sánchez, Pablo || -&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Rivero, Guillermo ||&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Sanz, Sergio || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Guasp Pérez, Jose || 6510&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Denche, Andrés Enrique || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Liniers Vazquez, Macarena || 0844&lt;br /&gt;
|-&lt;br /&gt;
| López Razola, Justo || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Martín Diaz, Fernando || -&lt;br /&gt;
|-&lt;br /&gt;
| Martín Hernandez, Felix || 6824&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Fernandez, Jose || 6646&lt;br /&gt;
|-&lt;br /&gt;
| Melón Blanco, Luis Jesús || 6285&lt;br /&gt;
|-&lt;br /&gt;
| Mirones Piulestan, Eloy || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Olivares Fernandez, Julian || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Pereira Gonzalez, Augusto || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Portas Ferreiro, Ana Belén || 0929&lt;br /&gt;
|-&lt;br /&gt;
| Pretty, David || -&lt;br /&gt;
|-&lt;br /&gt;
| Ratta Gutierrez, Giuseppe A. || 7918&lt;br /&gt;
|-&lt;br /&gt;
| Redondo Redondo, Mariano || 6287&lt;br /&gt;
|-&lt;br /&gt;
| Rios Marquez, Luis Maria || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Rojo Lozano, Beatriz || 0916&lt;br /&gt;
|-&lt;br /&gt;
| Romero Gonzalez, Jesus Antonio || 0852&lt;br /&gt;
|-&lt;br /&gt;
| Ros Vivancos, Alfonso || 6642  || Sala Control 6828;  || Lab. &amp;amp;mu;Ondas 6808&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Sarabia, Emilio || 6762&lt;br /&gt;
|-&lt;br /&gt;
| Sebastian Alfaro, José Antonio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Tabarés Vazquez, Francisco Luis || 6458&lt;br /&gt;
|-&lt;br /&gt;
| Tafalla García, David || 0843&lt;br /&gt;
|-&lt;br /&gt;
| Tesfaye Girma, Wurgie || -&lt;br /&gt;
|-&lt;br /&gt;
| Tolkachev, Alexander || 6828&lt;br /&gt;
|-&lt;br /&gt;
| Vega Sánchez, Jesús Antonio || 6474&lt;br /&gt;
|-&lt;br /&gt;
| Velasco de la Cuadra, Gregorio || 6819&lt;br /&gt;
|-&lt;br /&gt;
| Sala operación NBI  || 6851&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Fusion theory unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Castejón,  Francisco,  Head Investigator  || 6504&lt;br /&gt;
|-&lt;br /&gt;
| Barrera Orte,  Laura || 0917&lt;br /&gt;
|-&lt;br /&gt;
| de Bustos Molina,  Andrés || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Rubio,  Iván || 6739&lt;br /&gt;
|-&lt;br /&gt;
| García Regaña,  José Manuel || 6687&lt;br /&gt;
|-&lt;br /&gt;
| Gómez Iglesias,  Antonio || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Jiménez Aparicio,  Juan Antonio || 6503&lt;br /&gt;
|-&lt;br /&gt;
| López Bruna,  Daniel || 6638&lt;br /&gt;
|-&lt;br /&gt;
| López Fraguas,  Antonio || 0850&lt;br /&gt;
|-&lt;br /&gt;
| [[User:Esolano|Rodríguez-Solano Ribeiro,  Emilia]]|| 6153&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez González,  Edilberto || 6162&lt;br /&gt;
|-&lt;br /&gt;
| Velasco Garasa,  José Luis || 6640&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Engineering unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Alonso,  José Javier,  Head Investigator  || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Álvarez Benitez,  Pio || 6684&lt;br /&gt;
|-&lt;br /&gt;
| Botija Pérez,  José || 6329&lt;br /&gt;
|-&lt;br /&gt;
| Carrasco García,  Ricardo || 7928&lt;br /&gt;
|-&lt;br /&gt;
| Kirpitchev,  Igor || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Lapayese Puebla,  Fernando || 0928&lt;br /&gt;
|-&lt;br /&gt;
| Medrano Casanova,  Mercedes || 6639&lt;br /&gt;
|-&lt;br /&gt;
| Méndez Montero,  Purificación || 6337&lt;br /&gt;
|-&lt;br /&gt;
| Pacios Rodríguez,  Luis || 6644&lt;br /&gt;
|-&lt;br /&gt;
| de la Peña Gómez,  Ángel || 6644&lt;br /&gt;
|-&lt;br /&gt;
| Pérez Pichel,  Germán || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Queral Mas,  Vicente || 6419&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Rivero,  Francisco || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rincón Rincón,  María Esther || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Soleto Palomo,  M. Alfonso || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Weber Suárez,  Moisés || 6636&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Technology division ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Ibarra Sánchez,   Ángel,  Head Investigator  || 6507&lt;br /&gt;
|-&lt;br /&gt;
| Hodgson Hampson,  Eric Richard || 6202&lt;br /&gt;
|-&lt;br /&gt;
| Arroyo Macias,   José Manuel || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Brañas Lasala,   Beatriz || 6289&lt;br /&gt;
|-&lt;br /&gt;
| Calvo Pinto,   Julio || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carella,   Elisabetta || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Carmona Torres,   José Miguel || 6640&lt;br /&gt;
|-&lt;br /&gt;
| Casal Iglesias,   Natalia || 6636&lt;br /&gt;
|-&lt;br /&gt;
| Castro Lobera, Paloma || 0852 ||7852&lt;br /&gt;
|-&lt;br /&gt;
| Cuarental García,   Irene || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Delgado Bueno,   Diego || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Berceruelo,   Iván || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Fernández Paredes,   Mª. Pilar || 2581&lt;br /&gt;
|-&lt;br /&gt;
| García Gonzalez,   Juan Manuel || 6578&lt;br /&gt;
|-&lt;br /&gt;
| García Sanz,   Ángela || 6335&lt;br /&gt;
|-&lt;br /&gt;
| Gómez-Ferrer Herran,   Begoña || 2574 || Lab. 6512&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez López,   Raúl || 6641&lt;br /&gt;
|-&lt;br /&gt;
| Gonzalez Viada,   María || 2582&lt;br /&gt;
|-&lt;br /&gt;
| Hernandez Diaz,   Mª. Teresa || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Jimenez Baena,   Francisco M. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Juanas Fernandez,   Jesús || 2579&lt;br /&gt;
|-&lt;br /&gt;
| León Pichel,   Mónica || 2574&lt;br /&gt;
|-&lt;br /&gt;
| Malo Huerta,   Marta || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Manzano Santamaria,   Javier || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Martín Laso,   Montserrat || 6512&lt;br /&gt;
|-&lt;br /&gt;
| Martín Martinez,   Mª. Piedad || 2581&lt;br /&gt;
|-&lt;br /&gt;
| Martinez Alcalde,   Pablo Miguel || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Martinez-Albertos Bofarull,   José Luis || -&lt;br /&gt;
|-&lt;br /&gt;
| Molla Lorente,   Joaquín || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Moreno Tejera,   Carlos || 2579&lt;br /&gt;
|-&lt;br /&gt;
| Moroño Guadalajara,   Alejandro A. || 6372&lt;br /&gt;
|-&lt;br /&gt;
| Mota García,   Fernando || 6578&lt;br /&gt;
|-&lt;br /&gt;
| Ortíz,   Christophe || 6580&lt;br /&gt;
|-&lt;br /&gt;
| Oyarzabal Vicente,   Eider || -&lt;br /&gt;
|-&lt;br /&gt;
| Palermo,   Iole || 6784&lt;br /&gt;
|-&lt;br /&gt;
| Parro Albeniz,   Marcos || 0916 || 7916&lt;br /&gt;
|-&lt;br /&gt;
| Pérez López,   Mario || -&lt;br /&gt;
|-&lt;br /&gt;
| Ramos Gallardo,   Angel || 6361&lt;br /&gt;
|-&lt;br /&gt;
| Regidor Serrano,   David || 6584&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Salvador,   Diego || 6613&lt;br /&gt;
|-&lt;br /&gt;
| Rodríguez Sánchez,   Mª. Teresa || 6203&lt;br /&gt;
|-&lt;br /&gt;
| Sedano Miguel,   Luis Ángel || 0913 || 7913&lt;br /&gt;
|-&lt;br /&gt;
| Valle Paisan,   Francisco J. || 6204&lt;br /&gt;
|-&lt;br /&gt;
| Veredas Luque,   Gerardo || 6637&lt;br /&gt;
|-&lt;br /&gt;
| Vila Vazquez,   Rafael Alberto || 6580&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
=== Support unit ===&lt;br /&gt;
&lt;br /&gt;
{|  || -&lt;br /&gt;
|-&lt;br /&gt;
!width=&amp;quot;250&amp;quot; align=&amp;quot;left&amp;quot;|Name!!width=&amp;quot;50&amp;quot; align=&amp;quot;left&amp;quot;|Telephone&lt;br /&gt;
|-&lt;br /&gt;
| Dabbah Ainstein, Dina || 7851&lt;br /&gt;
|-&lt;br /&gt;
| Moreno García, Sabina || 6159&lt;br /&gt;
|-&lt;br /&gt;
| Romero Romero, Eulalia || 6161&lt;br /&gt;
|-&lt;br /&gt;
| Sánchez Rubio, Cristina || 6738&lt;br /&gt;
|-&lt;br /&gt;
| Torras Barneto, Mª Dolores || 6663&lt;br /&gt;
|}&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3866</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3866"/>
		<updated>2012-01-16T15:14:32Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Groups */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources.This experimental RAFM steel grade was obtained in a melting Pilot Plant by means of a High Vacuum induction melting furnace in order to assure a good control and to avoid possible impurities. The data obtained in the process of microstructural characterization (hardness or grain size), as in the mechanical tests put into practice at different temperatures as tensile test, facture test as well as the evaluation of a preliminary welding study, show a similar behavior to EUROFER 97-2.&lt;br /&gt;
. &amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|right|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# Goal Oriented Training Programme [[EUROBREED]]&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3865</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3865"/>
		<updated>2012-01-16T15:04:06Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* See also */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources.This experimental RAFM steel grade was obtained in a melting Pilot Plant by means of a High Vacuum induction melting furnace in order to assure a good control and to avoid possible impurities. The data obtained in the process of microstructural characterization (hardness or grain size), as in the mechanical tests put into practice at different temperatures as tensile test, facture test as well as the evaluation of a preliminary welding study, show a similar behavior to EUROFER 97-2.&lt;br /&gt;
. &amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|left|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# Goal Oriented Training Programme [[EUROBREED]]&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3864</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3864"/>
		<updated>2012-01-16T15:03:31Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Groups */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources.This experimental RAFM steel grade was obtained in a melting Pilot Plant by means of a High Vacuum induction melting furnace in order to assure a good control and to avoid possible impurities. The data obtained in the process of microstructural characterization (hardness or grain size), as in the mechanical tests put into practice at different temperatures as tensile test, facture test as well as the evaluation of a preliminary welding study, show a similar behavior to EUROFER 97-2.&lt;br /&gt;
. &amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|left|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# (GOT) Programme [[EUROBREED]]&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3862</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3862"/>
		<updated>2012-01-13T17:58:23Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The [[EUROBREED]] programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser &#039;&#039;&#039;Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes&#039;&#039;. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# Consolider INGENIO 2010 [[TECNO_FUS]] Programme&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3861</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3861"/>
		<updated>2012-01-13T17:57:20Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Objective */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The [[EUROBREED]] programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# Consolider INGENIO 2010 [[TECNO_FUS]] Programme&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3858</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3858"/>
		<updated>2012-01-13T08:32:24Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# Consolider INGENIO 2010 [[TECNO_FUS]] Programme&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3857</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3857"/>
		<updated>2012-01-13T08:31:05Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|left|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
== See also ==&lt;br /&gt;
# (GOT) Programme [[EUROBREED]]&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3856</id>
		<title>TECNO FUS</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=TECNO_FUS&amp;diff=3856"/>
		<updated>2012-01-13T08:27:17Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* External links */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Tecnofus a.jpg|thumb|420px|left]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
&lt;br /&gt;
TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by [http://www.micinn.es/ MICINN around 2,5 M€ and actually on new MINEYC]. It is oriented towards the development of technologies associated with the [[Breeding blanket]] key component of future Fusion Power Plants. &lt;br /&gt;
&lt;br /&gt;
Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee mainly but not only those objectives, already the following purposes:&lt;br /&gt;
&lt;br /&gt;
* The shielding of superconducting coils from the plasma (n, &amp;amp;gamma;) radiation with extreme shield factors (&amp;lt; mW cm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* The extraction and amplification of the fusion power (thermal loads in the first wall MWm&amp;lt;sup&amp;gt;-2&amp;lt;/sup&amp;gt; and volumetric (MWm&amp;lt;sup&amp;gt;-3&amp;lt;/sup&amp;gt;)&lt;br /&gt;
* Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.&lt;br /&gt;
&lt;br /&gt;
Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO_FUS, what is original is the development of the so called dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for &amp;quot;Doble Refrigerante Modular&amp;quot; of He/Pb-15.7Li.  &lt;br /&gt;
&lt;br /&gt;
Going into details it is worthwhile to mention some ongoing tasks:&lt;br /&gt;
&lt;br /&gt;
* ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation. &lt;br /&gt;
* CEIT has started the development of production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channels inserts (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb. The SiC is the Material of choice for its application due to its excellent  thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&lt;br /&gt;
&lt;br /&gt;
== Institutional participation ==&lt;br /&gt;
&lt;br /&gt;
[[File:ABEreciartu.jpg‎|220 px|thumb|BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs, Fusion Engineering and Design 86 (2011) 2526–2529]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Institutions involved are specialized Centres and Universities all over Spain, they are the following:&lt;br /&gt;
&lt;br /&gt;
* [http://www.ceit.es/ Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT)] of the Universidad de Navarra (UNAV)&lt;br /&gt;
* [http://www.upcomillas.es/ Universidad Pontificia de Comillas (ETSII-COMILLAS)]&lt;br /&gt;
* [http://www.ehu.es/ Universidad del País Vasco (UPV-EHU)] &lt;br /&gt;
* [http://www.iqs.es/ Instituto Químico de Sarriá -IQS-(Universidad Ramón Llull)]&lt;br /&gt;
* [http://www.itma.es/ Instituto Tecnológico de Materiales (ITMA) ] (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the [http://www.uniovi.es/ Universidad de Oviedo (UNIOVI)]&lt;br /&gt;
* [http://www.ucm.es/ Universidad Complutense de Madrid (UCM)]&lt;br /&gt;
* [http://www.uned.es/ Universidad Nacional de Educación a Distancia (UNED)] &lt;br /&gt;
* [http://www.upc.es/ Universidad Politécnica de Cataluña (UPC)]&lt;br /&gt;
* [http://www.upm.es/ Universidad Politécnica de Madrid (UPM)]&lt;br /&gt;
The work is coordinated by [[CIEMAT]], acting as Legal Management Entity, such that the Head of the National Fusion Laboratory  [[Laboratorio Nacional de Fusión|LNF]] is also the Research Coordinator. &lt;br /&gt;
The project includes a Technical Secretary with specific support an a CAD Office.&lt;br /&gt;
&lt;br /&gt;
== Tasks ==&lt;br /&gt;
[[File:JJuanasIFernandez.jpg‎|330 px|thumb|right|Detail of Modular Dualcoolant with He(red)/LiPb(blue) tubes over a segment of three modules and their dimensions (J.Juanas, I.Fernández, G.Veredas, L.Sedano CIEMAT)]]&lt;br /&gt;
&lt;br /&gt;
Leadership researchers are responsible for the following 9 tasks:&lt;br /&gt;
&lt;br /&gt;
# Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,&lt;br /&gt;
# Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,&lt;br /&gt;
# Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,&lt;br /&gt;
# Production of DRM functional and structural materials,&lt;br /&gt;
# Design of technologies and Plant Systems,&lt;br /&gt;
# Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,&lt;br /&gt;
# Safety analysis and the Environmental Impact of the DRM He/LiPb system,&lt;br /&gt;
# DEMO plasmae and  reactor specifications and&lt;br /&gt;
# Blanket and Systems Integration and engineering survey&lt;br /&gt;
&lt;br /&gt;
In each task may be more than one working Group.&lt;br /&gt;
&lt;br /&gt;
== Groups ==&lt;br /&gt;
[[File:Diagrama_de_Fase_del_Li-Pb.png‎|320 px|thumb|left|Diagrama de Fase del LiPb(I.Barrena et al. UCM) &amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
Experts Leadership researchers are responsible for the following 19 groups:&lt;br /&gt;
&lt;br /&gt;
# WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]]&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/Abstract_ISFNT10.pdf I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano, &#039;&#039;Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO&#039;&#039; (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003036 J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano, &#039;&#039;Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2293–2296]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;&lt;br /&gt;
# WG 3: CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems, (Thermal Hydraulics), within the subtask 3.1&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0022311511001930 J. Fradera, L. Sedano, E. Mas de les Valls, L. Batet, &#039;&#039;Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules&#039;&#039;, Journal of Nuclear Materials &#039;&#039;&#039;417&#039;&#039;&#039; (2011) 739–742]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG 4: Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary   systems, (Magneto Hydrodynamics, subtask 3.2)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003449 E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, &#039;&#039;Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2326–2329]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG5: Production of Eurofer steels batches at laboratory, within task 4.1 (Actually strong added value of ASTURFER ® made mainly but not only with ITMA resources&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-778336.pdf A.Morán, J. Belzunce, J.M. Artímez, &#039;&#039;Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico&#039;&#039;, ASTURFER®]&lt;br /&gt;
&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG6: Production of &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li and eutectic LiPb batches at laboratory, within subtask 4.2 (Actually added value of 15 batches of LiPb fused and refused in different conditions made at UCM and impurities analysed with the ICP-MS of CIEMAT)&amp;lt;ref&amp;gt; [[doi::10.1016/j.fusengdes.2010.11.028|A.I.Barrado, M.Fernández, E.Conde, A.Quejido, J.Quiñones, L.Sedano, &#039;&#039;Preliminary studies of in-cell electrophoresis as &amp;lt;sup&amp;gt;6&amp;lt;/sup&amp;gt;Li enrichment technique&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design, Volume &#039;&#039;&#039;86&#039;&#039;&#039;, Issued 14 Jan 2011, Pages 2662-2665]]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://dl.dropbox.com/u/7419832/FusionWiki/UCM%20Informe%20del%20Proyecto%20Tecno-fus.pdf M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS]&amp;lt;/ref&amp;gt;];&lt;br /&gt;
# WG7: Production of SiC subtask 4.3; the objective of this task is the production routes of ceramic materials based on porous SiC and composite SiCf/SiC, for application as insulating channel inserts (or insulating FCI). This is based on the Modular Dual coolant He/LiPb or TECNO-FUS DRM Liquid Metal. The SiC has been choice due its excellent thermal stability, mechanical and chemical characteristics at high temperatures. Its low thermal expansion, good thermal shock resistance, low corrosion in Pb-15.7Li, low activation and good resistance to neutron irradiation make it the correct working material.&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611003644 Ainhoa Bereciartu, Nerea Ordás, Carmen García-Rosales, Alejandro Moroño, Marta Malo, Eric R. Hodgson, Jordi Abellà, Luis Sedano, &#039;&#039;Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2526–2529]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.ceit.es/index.php?option=com_content&amp;amp;view=article&amp;amp;id=91&amp;amp;Itemid=206 TECNO_FUS Project in CEIT website]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);&lt;br /&gt;
# WG9: Electrical Properties characterisation of the Modular dual coolant DRM He/LiPb functional and structural materials, mainly but not only SiC coming from subtask 4.3) within subtask 4.5;&lt;br /&gt;
# WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within  subtask 4.6&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-10%20_205_.pdf  G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, &#039;&#039;TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;&lt;br /&gt;
# WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://upcommons.upc.edu/pfc/handle/2099.1/ &#039;&#039;Modelat del transport de triti en un canal de l&#039;embolcall regenerador de triti d&#039;un reactor de fusió DT,&#039;&#039; PFC Pau Bermúdez García. Dec-2010]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG13: The aim of this Group is the Control and monitoring technologies within subtask 5.2 oriented to specific tritium monitoring an control developments: 1. Development of H-partial pressure sensors, 2. Li-title electrochemical sensor and Li-title on-line adjustment techniques, and 3. Composition evolution sensing)&amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S092037961100041X P. Serret, S. Colominas, G. Reyes, J. Abellà, &#039;&#039;Characterization of ceramic materials for electrochemical hydrogen sensors&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2446–2449]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-334445.pdf L. Llivina, S. Colominas, J. Abellà, &#039;&#039;Síntesis y caracterización de cerámicas para sensores de hidrógeno&#039;&#039;]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG14: Design of technologies and Plant Systems, which purpose are the Power Conversion  (helium cycles and CO2 cycles) and the new energy vectors for Fusion, within subtask 5.3&amp;lt;ref&amp;gt;[[doi::10.1016/j.fusengdes.2011.02.010|&lt;br /&gt;
J.I.Linares, L.E.Herranz, B.Y.Moratilla, I.P.Serrano, &#039;&#039;Power conversion systems based on Brayton cycles for fusion reactors&#039;&#039;, 26&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Fusion Technology, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2735–2738]] &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://dl.dropbox.com/u/7419832/FusionWiki/Linares_JEPE.pdf J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, &#039;&#039;Brayton Power Cycles For Electricity Generation From Fusion Reactors&#039;&#039;, Jan. 2010, Volume &#039;&#039;&#039;4&#039;&#039;&#039;, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA]&amp;lt;/ref&amp;gt;;&lt;br /&gt;
# WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;&lt;br /&gt;
# WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);&lt;br /&gt;
# WG17: Group responsible for the development of the Environmental Impact of the of fusion power plant systems mainly but not only in the atmosphere, running some numerical weather prediction model coupled with some dispersion model to analyse tritium species concentration in air and associated doses, within the subtask 7.2&amp;lt;ref&amp;gt;[http://www.reunionanualsne.es/sites/default/files/doc37/ponencias/983377-886491.pdf P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation&#039;&#039;]&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt; [http://www.new.ans.org/pubs/journals/fst/a_12665 P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, &#039;&#039;Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release&#039;&#039;, Fusion Science and Technology &#039;&#039;&#039;60&#039;&#039;&#039;, 4 (2011) 1284-1287]&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?arnumber=6052268 Castro, P.,   Velarde, M.,   Ardao, J., Perlado, J.M., Sedano, L., &#039;&#039;Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues&#039;&#039;, Fusion Engineering (SOFE), 2011 IEEE/NPSS 24&amp;lt;sup&amp;gt;th&amp;lt;/sup&amp;gt; Symposium on Issue Date: 26-30 June 2011 ] &amp;lt;/ref&amp;gt; ;&lt;br /&gt;
# WG18: DEMO plasmae and reactor specifications as Task 8.&lt;br /&gt;
# WG19: Group Responsible for complete task 9 with the purpose of the Blanket and Systems Integration and engineering survey (mainly but not only the RAFM).&lt;br /&gt;
[[File:Libretto41_42.png‎|420 px|thumb|left|Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) &amp;lt;ref&amp;gt;[http://www.sciencedirect.com/science/article/pii/S0920379611002250 P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, &#039;&#039;LIBRETTO-4: Understanding and modeling tritium transport under irradiation&#039;&#039;, Fusion Engineering and Design &#039;&#039;&#039;86&#039;&#039;&#039; (2011) 2374–2377] &amp;lt;/ref&amp;gt;]]&lt;br /&gt;
&lt;br /&gt;
== External links ==&lt;br /&gt;
# [http://www.reunionanualsne.es/sites/default/files/doc37/sinopsis/11-01%20_190_.pdf J. Sánchez, L. A. Sedano, E. R. Hodgson, M. Victoria, J. Sanz, M. Chiumenti,J. Hernández, F. Reventós, R. Codina, A. Ibarra, J. Belzunce, J. Quiñones, C.Gª Rosales, P.Fernández, A. Moroño, F. Legarda, J. M. Perlado, J. Sempere, J.Abellà, J. I. Linares, J. Vega, L.E. Herranz, J. Mª. Martínez-Val, E. Mínguez,, J. Dies, J.Alonso(and 90 researches from 13 Institutions,)PROGRESS IN TECNO_FUS PROGRAMME FOR DUALCOOLANT ADVANCED BREEDING BLANKET DEVELOPMENTS]&lt;br /&gt;
# [http://www.upm.es/observatorio/vi/actividad.jsp?id_actividad=66623 L.Sedano, TECNO_FUS: A Breeding Blanket NFT programme developing dual functional He/Pb15.7Li systems engineering &amp;amp; associated underlying technologies]&lt;br /&gt;
# [http://www-fusion.ciemat.es/LMBW/detailed_programme03.shtml International Workshop on Liquid Metal Breeder Blankets. 23-24 September 2010, CIEMAT, Madrid]&lt;br /&gt;
# [http://www.tecnofus.net TECNO_FUS website]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3855</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3855"/>
		<updated>2012-01-13T08:21:26Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Institutional Participation */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3854</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3854"/>
		<updated>2012-01-13T08:20:42Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Institutional Participation */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* [[NRG]]/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3853</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3853"/>
		<updated>2012-01-13T08:20:08Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Institutional Participation */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy,CCFE UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3852</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3852"/>
		<updated>2012-01-13T08:14:18Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster &#039;&#039;&#039;Session 2-080&#039;&#039;&#039;&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3849</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3849"/>
		<updated>2012-01-12T13:55:43Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3848</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3848"/>
		<updated>2012-01-12T13:55:05Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3847</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3847"/>
		<updated>2012-01-12T13:54:29Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3846</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3846"/>
		<updated>2012-01-12T13:54:10Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3845</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3845"/>
		<updated>2012-01-12T13:53:37Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3844</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3844"/>
		<updated>2012-01-12T13:53:23Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3843</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3843"/>
		<updated>2012-01-12T13:52:48Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3842</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3842"/>
		<updated>2012-01-12T13:52:17Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3841</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3841"/>
		<updated>2012-01-12T13:51:46Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3840</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3840"/>
		<updated>2012-01-12T13:51:29Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3839</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3839"/>
		<updated>2012-01-12T13:51:00Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3838</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3838"/>
		<updated>2012-01-12T13:50:42Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;M.Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3837</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3837"/>
		<updated>2012-01-12T13:50:06Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3836</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3836"/>
		<updated>2012-01-12T13:49:42Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3835</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3835"/>
		<updated>2012-01-12T13:49:11Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3834</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3834"/>
		<updated>2012-01-12T13:48:49Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3833</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3833"/>
		<updated>2012-01-12T13:48:16Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3832</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3832"/>
		<updated>2012-01-12T13:47:45Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Introduction */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131[http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html] &amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3831</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3831"/>
		<updated>2012-01-12T13:47:19Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3830</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3830"/>
		<updated>2012-01-12T13:46:09Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Introduction */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&amp;lt;ref&amp;gt;L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3829</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3829"/>
		<updated>2012-01-12T13:45:25Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3828</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3828"/>
		<updated>2012-01-12T13:44:47Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&amp;lt;ref&amp;gt;I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325 (SOFT-26 Proceedings, P2-001&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3827</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3827"/>
		<updated>2012-01-12T13:44:02Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
#EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3826</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3826"/>
		<updated>2012-01-12T13:43:22Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &amp;lt;ref&amp;gt;G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &amp;lt;/ref&amp;gt;&lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3825</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3825"/>
		<updated>2012-01-12T13:42:49Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3824</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3824"/>
		<updated>2012-01-12T13:42:30Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt; C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;/ref&amp;gt;&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management &amp;lt;ref&amp;gt;L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3823</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3823"/>
		<updated>2012-01-12T13:40:16Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&amp;lt;ref&amp;gt;Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&amp;lt;ref&amp;gt;#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3822</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3822"/>
		<updated>2012-01-12T13:39:09Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&lt;br /&gt;
#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3821</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3821"/>
		<updated>2012-01-12T13:38:38Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&lt;br /&gt;
#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&amp;lt;ref&amp;gt;P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
#Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3820</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3820"/>
		<updated>2012-01-12T13:38:10Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&lt;br /&gt;
#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
#Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3819</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3819"/>
		<updated>2012-01-12T13:37:42Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* Tasks (identified as Work Packages) */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&lt;br /&gt;
#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &amp;lt;ref&amp;gt;#Sander Van Til “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (15 Sept. 2011) Poster Session 3-021 &amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
&lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
#Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&lt;br /&gt;
#P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
	<entry>
		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3818</id>
		<title>EUROBREED</title>
		<link rel="alternate" type="text/html" href="http://wiki.fusenet.eu/fusionwiki/index.php?title=EUROBREED&amp;diff=3818"/>
		<updated>2012-01-12T13:37:12Z</updated>

		<summary type="html">&lt;p&gt;Castro: /* References */&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;[[File:Eurobreed.png|right]]&lt;br /&gt;
== Introduction ==&lt;br /&gt;
The Goal Oriented Training Programme EUROBREED or “[[Breeding blanket]] Developments for Fusion Reactors” is a programme dedicated to the educational and technical training of new experts in several disciplines involved in the field of Breeding Blanket in order to give at the same time a workforce support to the [[Euratom]] associations involved. &lt;br /&gt;
At its meeting in Otaniemi 4-5 June 2007, the [[EFDA]] Steering Committee approved the EFDA 2008 Work Programme, including the implementation of training programmes in the field of fusion energy research. This Task Agreement covers a training activity in the field of Breeding Blanket called EUROBREED (Breeding Blanket Developments for Fusion Reactors) and will be implemented on the basis of the provisions given in Art 7 of the EFDA Agreement. This activity under Additional Support in this Task Agreement was recommended by the EFDA Steering Committee at its meeting of 10-11th March 2008 in Ljubljana (EFDA (08) 36/4.6).&lt;br /&gt;
&lt;br /&gt;
== Objective ==&lt;br /&gt;
The overall objective of the goal oriented training (GOT) Programme EUROBREED is helping to provide the necessary broad expert basis to successfully conduct the European Breeding blanket development programme along with [[ITER]] and the developments beyond ITER, i.e., for a fusion power reactor, comprising the development of the optimum breeder and neutron multiplier materials, the design of specific breeder blanket components for future fusion reactors, and testing the breeding blanket in ITER. The EUROBREED programme, jointly conducted since end 2008 by KIT, AEUL, CEA, [[CIEMAT]], ENEA, FOM/NRG, HAS and UKAEA, consists of eight Work Packages (WP) entailing each a different discipline (WP, see Table 1). Each of the WPs represents a training programme unit for a trainee that is employed in the WP leader association. The basis trainee’s programme consists of educational units (about 1/3 of the time) in which the trainee attends courses in fusion technology and on the particular research field. The rest of the time is dedicated to a participation to technical work in which the trainee proceeds along, and enhances, already existing projects of the associations in the framework of the European Breeder Blanket Programme.&lt;br /&gt;
&lt;br /&gt;
== Institutional Participation ==&lt;br /&gt;
[[File:HCPByHCLL.png‎|520 px|thumb|Views of the two Test Blanket Module (TBM) Helium Cooled concepts developed by the European Breeder Blanket programme: the HCPB (Pebble Bed) and the HCLL (Lead Lithium) managed at KIT and CEA respectively &amp;lt;ref&amp;gt;[Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)&amp;lt;/ref&amp;gt;]]&lt;br /&gt;
* CEA (Commissariat à l’Energie Atomique, France) &lt;br /&gt;
* ENEA (FTU) (Ente per le Nuove Tecnologie, l&#039;Energia e l&#039;Ambiente Frascati - Italy) &lt;br /&gt;
* [[Laboratorio Nacional de Fusión]] (Asociación [[Euratom]]-[[CIEMAT]], Madrid - Spain) &lt;br /&gt;
* Forschungszentrum Karlsruhe (FZK): Karlsruher Institut für Technologie (KIT)&lt;br /&gt;
* University of Latvia (LU) - [[Euratom]] Association (European Atomic Energy Community) &lt;br /&gt;
* HAS (Hungarian Academy of Sciences)/BUTE (Budapest University of Technology and Economics)&lt;br /&gt;
* NRG/FOM (Nuclear Services for Energy, Environment and Health)&lt;br /&gt;
* [[EFDA]]-JET (Culham Centre for Fusion Energy, UK)&lt;br /&gt;
&lt;br /&gt;
== Tasks (identified as Work Packages) ==&lt;br /&gt;
&lt;br /&gt;
{| class=&amp;quot;wikitable&amp;quot;  align=&amp;quot;center&amp;quot; border=&amp;quot;1&amp;quot;&lt;br /&gt;
!&#039;&#039;WP ID&#039;&#039;                           !!&#039;&#039;Leader Org.&#039;&#039;!!&#039;&#039;WP Description&#039;&#039;&lt;br /&gt;
|-&lt;br /&gt;
|WP1 ||KIT ||Design, procurement and test of solid breeder units &amp;lt;ref&amp;gt;F. Hernandez, F. Cismondi, B. Kiss , “FLUID DYNAMIC AND THERMAL ANALYSES OF THE HCPB TBM BREEDER UNITS” 26th Symposium on Fusion Technology, (SOFT-26 Proceedings, P1-137)&lt;br /&gt;
&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket&amp;lt;ref&amp;gt;M. Kolb et Al., “Enhanced fabrication process for lithum orthosilicate pebbles as breeding material”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151 (SOFT-26 Proceedings, P1-139)&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor &amp;lt;ref&amp;gt;#C. Fausser et Al., “numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield &amp;amp; preliminary FNG HCLL TBM mock-up experiments”. Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138, (SOFT-26 Proceedings, P2-016)&lt;br /&gt;
#L.Commin et Al., “TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT” 26th Symposium on Fusion Technology Proceedings, P1-030&amp;lt;/ref&amp;gt;&lt;br /&gt;
|-&lt;br /&gt;
|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management&lt;br /&gt;
|-&lt;br /&gt;
|WP5 ||HAS ||Measurement techniques development for breeder blankets&lt;br /&gt;
|-&lt;br /&gt;
|WP6 ||NRG ||Pebble bed nuclear performance testing &lt;br /&gt;
|-&lt;br /&gt;
|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling&lt;br /&gt;
|-&lt;br /&gt;
|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials &lt;br /&gt;
|}&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;br /&gt;
# EFDA WORKPROGRAMME 2008 Goal Oriented Training Programme. TASK AGREEMENT WP08-GOT-EUROBREED, 14 July 2008.&lt;br /&gt;
#L. V. Boccaccini et al., “THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED” 26th Symposium on Fusion Technology, P2-131&lt;br /&gt;
#Dereck Stork, “Technical Challenges on the path to DEMO” Int. Meet. MFE Roadmapping in the ITER era. PPL 11-16 Sept. (2011 26th Symposium on Fusion Technology, SOFT-26. Porto, Portugal. Sep 27-Oct 1(2010)http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html &lt;br /&gt;
&lt;br /&gt;
#I. Rovni et Al., “An improved method of detector material selection for multiple foil activation measurements in the TBMs”. Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325, , (SOFT-26 Proceedings, P2-001)&lt;br /&gt;
#S. van Til et Al., “Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor”. Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261 (SOFT-26, P3-138)&lt;br /&gt;
#P.Martínez et Al., “LIBRETTO-4: Understanding and modeling tritium transport under irradiation”. Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377, (SOFT-26, P4-016)&lt;br /&gt;
#E. Pajuste et Al., “Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing”. Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128 (Proceedings of the SOFT-26, P1-144) ENYGF-37. Prague, Check R. 17-22 May (2011) http://www.enygf.eu/programme/proceedings.html &lt;br /&gt;
#F. Hernández, F. Cismondi, B. Bliss, “Design Cycle of a Breeder Unit Mock-up for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) for ITER”&lt;br /&gt;
#S. van Til, “Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle”&lt;br /&gt;
#P. Martínez, C. Moreno, L.A. Sedano, “OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT”&lt;br /&gt;
#G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs, “STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS” 10th International Symposium on Fusion Nuclear Technologies, ISFNT-10. 11-16 Sep. 2011 Portland, Oregon http://www.isfnt-10.org/Program-schedule.html &lt;br /&gt;
#Francisco Hernandez “Thermo-mechanical Analyses and Assessment with Respect the Design Codes and Standards of the HCPB Breeder Unit”. (14 Sept. 2011) Poster Session 2-026&lt;br /&gt;
#Matthias Kolb “Synthesis of Tritium Breeder Ceramics from Metallic Lithium”. (13 Sept. 2011) Poster Session 1-060&lt;br /&gt;
#Clement Fausser “Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes”. (14 Sept. 2011) Poster Session 2-080&lt;br /&gt;
#P.Miguel Martinez Alcalde “Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools” (13 &amp;amp; 15 Sept. 2011) Poster S. 1-055 and 3-051&lt;/div&gt;</summary>
		<author><name>Castro</name></author>
	</entry>
</feed>