EUROBREED: Difference between revisions

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.  

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).<ref>L. V. Boccaccini et al., ''THE EFDA GOAL ORIENTED TRAINING PROGRAM EUROBREED'', 26th Symposium on Fusion Technology, [http://portal.ipfn.ist.utl.pt/soft2010_abstractbook/contrib.html P2-131] </ref>

[[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 <ref>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)</ref>]]

|WP1 ||KIT ||Design, procurement and test of solid breeder units <ref>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)

</ref><ref>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</ref><ref>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''</ref>

|WP2 ||KIT ||Pebble bed development and testing for the EU solid breeder blanket<ref>M. Kolb et Al., ''Enhanced fabrication process for lithum orthosilicate pebbles as breeding material'', [[doi:10.1016/j.fusengdes.2011.01.104|Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2148–2151]] (SOFT-26 Proceedings, P1-139)</ref>

|WP3 ||CEA ||Neutronics and radiation protection shielding design of the HCLL reactor <ref> C. Fausser et Al., ''numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield & preliminary FNG HCLL TBM mock-up experiments'', [[doi:10.1016/j.fusengdes.2011.04.018|Fusion Engineering and Design (October 2011), 86 (9-11), pg. 2135-2138]] (SOFT-26 Proceedings, P2-016)</ref><ref>Clement Fausser '''Tokamak D-T Neutron Source Models for Different Plasma Physics Confinement Modes''. (14 Sept. 2011) Poster Session 2-080</ref>

|WP4 ||CEA ||TBM integration in Port Plug with engineering design and interfaces management <ref>L.Commin et Al., ''TEST BLANKET MODULE PIPE FOREST INTEGRATION IN ITER EQUATORIAL PORT'', 26th Symposium on Fusion Technology Proceedings, P1-030</ref>

|WP5 ||HAS ||Measurement techniques development for breeder blankets<ref>I. Rovni et Al., ''An improved method of detector material selection for multiple foil activation measurements in the TBMs'', [[doi:10.1016/j.fusengdes.2011.02.031|Fusion Engineering and Design, V.86, Issues 9–11, October 2011, Pages 2322–2325]] (SOFT-26 Proceedings, P2-001)</ref>

|WP6 ||NRG ||Pebble bed nuclear performance testing <ref>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 </ref><ref>S. van Til et Al., ''Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor'', [[doi:10.1016/j.fusengdes.2011.01.079|Fusion Engineering and Design, V. 86, Issues 9–11, October 2011, Pages 2258–2261]] (SOFT-26, P3-138)

</ref><ref>M.Kolb, ''Synthesis of Tritium Breeder Ceramics from Metallic Lithium'', (13 Sept. 2011) Poster Session 1-060

</ref><ref>S. van Til, ''Nuclear Performance Testing of Functional Materials for the Fusion Fuel Cycle''

|WP7 ||CIEMAT ||Tritium transport predictive modelling  tools for Breeding Blanket design analyses and system modelling<ref>P.Miguel Martinez Alcalde, ''Optimizing Tritium Extraction from a Permeator Against Vacuum (PAV) by Dimensional Design Using Different Tritium Transport Modeling Tools'', (13 & 15 Sept. 2011) Poster S. 1-055 and 3-051

</ref><ref>P.Martínez et Al., ''LIBRETTO-4: Understanding and modeling tritium transport under irradiation'', [[doi:10.1016/j.fusengdes.2011.02.055|Fusion Engineering and Design  V. 86, Issues 9–11, October 2011, Pages 2374–2377]] (SOFT-26, P4-016)</ref><ref>P. Martínez, C. Moreno, L.A. Sedano, ''OVERVIEW OF DEVELOPMENTS OF TRITIUM TRANSPORT MODELING TOOLS FOR FUSION REACTOR DESIGN AT CIEMAT'', ENYGF-37. Prague, Check R. 17-22 May (2011) [http://www.enygf.eu/programme/proceedings.html link]</ref>

|WP8 ||AEUL ||Properties and diffusion of tritium accumulated in fusion reactor materials <ref>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 </ref><ref>E. Pajuste et Al., ''Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing'', [[doi:10.1016/j.fusengdes.2011.02.058|Fusion Engineering and Design V. 86, Issues 9–11, October 2011, Pages 2125–2128]] (Proceedings of the SOFT-26, P1-144)  </ref>