TECNO FUS

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Introduction

TECNO_FUS is a Programme financed by the Spanish Government (by means of a CONSOLIDER INGENIO 2010 grant CSD2008-0079 by 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.

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:

  • The shielding of superconducting coils from the plasma (n, γ) radiation with extreme shield factors (< mW cm-3)
  • The extraction and amplification of the fusion power (thermal loads in the first wall MWm-2 and volumetric (MWm-3)
  • Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement of the DT fusion reactors.

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 "Doble Refrigerante Modular" of He/Pb-15.7Li.

Going into details it is worthwhile to mention some ongoing tasks:

  • ITMA has started the development of a spanish RAFM ASTURFER ® and CIEMAT is making its metallurgical characterisation.
  • 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.

Institutional participation

BSE-SEM images of polished cross sectors after corrosion test (A.Bereciartu et al. CEIT [1]

Institutions involved are specialized Centres and Universities all over Spain, they are the following:

The work is coordinated by CIEMAT, acting as Legal Management Entity, such that the Head of the National Fusion Laboratory LNF is also the Research Coordinator. The project includes a Technical Secretary with specific support an a CAD Office.

Tasks

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)

Leadership researchers are responsible for the following 9 tasks:

  1. Computational neutronics of Modular Dualcoolant -DRM-refrigerated by He and by LiPb,
  2. Integral structural design Thermomecanic (TM) and EM of the Modular Dualcoolant DRM He/LiPb,
  3. Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and its auxiliary systems,
  4. Production of DRM functional and structural materials,
  5. Design of technologies and Plant Systems,
  6. Breeding blanket diagnostic and control and Data Acquisition (CODAC) architectures,
  7. Safety analysis and the Environmental Impact of the DRM He/LiPb system,
  8. DEMO plasmae and reactor specifications and
  9. Blanket and Systems Integration and engineering survey

In each task may be more than one working Group.

Groups

Diagrama de Fase del LiPb(I.Barrena et al. UCM) [2]

Experts Leadership researchers are responsible for the following 19 groups:

  1. WG 1: Computational neutronics of Modular Dual coolant -DRM-refrigerated by He and by LiPb box]][3][4];
  2. WP 2: Responsible for the Integral structural design by Thermal Mechanics and Electromagnetic structural design, within task 2;
  3. 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[5];
  4. 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)[6];
  5. 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[7];
  6. WG6: Production of 6Li 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)[8]];
  7. 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.[9][10];
  8. WG8: Metallurgical characterisation of the Eurofer steels batches at laboratory, (subtask 4.1. Actually characterisation of the ASTURFER ® batches);
  9. 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;
  10. WG10: Tritium properties characterisation by means of the selected technologies by EHU-UPV, mainly but not only IDE, within subtask 4.6[11];
  11. WG11: Computational characterisation of eutectic LiPb, within subtask 4.7;
  12. WG12: Devoted to the design of tritium transport analysis and corresponding FPD, within subtask 5.1 [12][13];
  13. 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)[14][15];
  14. 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[16];
  15. WG15: Breeding blanket diagnostics and Control and Data Acquisition (CODAC) architectures;
  16. WG16: Safety analysis of the DRM He/LiPb system (subtask 7.1);
  17. 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[17][18] ;
  18. WG18: DEMO plasmae and reactor specifications as Task 8.
  19. 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).
Evolution of the Tritium transferece rate in a first cycle september 2005 of HRF Petten(P.Martínez,CIEMAT N.Moral et al. UPM) [19]

External links

References

  1. ↑ 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
  2. ↑ M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS
  3. ↑ I. Palermo, J.M. Gómez-Ros, G. Veredas, J. Sanz, L. Sedano. Neutronic Design Analysis for a Dual-Coolant Blanket concept: Optimization for a Fusion Reactor DEMO (ISFNT-10: International Symposium on Fusion Nuclear Technology, Portland, Oregon, USA, 11-16 September 2011) sent to Fusion Eng. Des. (2012)
  4. ↑ J.P. Catalán, F. Ogandoa, J. Sanz, I. Palermo, G. eredas, J.M. Gómez-Ros, L. Sedano,Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO, Fusion Engineering and Design 86 (2011) 2293–2296
  5. ↑ J.Fradera,L. Sedano, E. Mas de les Valls L. Batet, Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules, Journal of Nuclear Materials 417 (2011) 739–742
  6. ↑ E. Mas de les Valls, L. Batet, V. de Medina, J. Fradera, L.A. Sedano, Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling, Fusion Engineering and Design 86 (2011) 2326–2329
  7. ↑ A.Morán, J. Belzunce, J.M. Artímez, Producción y cualificación, para aplicaciones de Fusión, de un acero de baja actividad ferrítico-martensítico, ASTURFER®
  8. ↑ M.I.Barrena, J.M.Gómez de salazar, Alicia Soria, Laura Pascual, Informe del Proyecto CONSOLIDER INGENIO 2010 TECNO-FUS
  9. ↑ 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
  10. ↑ TECNO_FUS Project in CEIT website
  11. ↑ G. Alberro, I. Peñalva, J. Aranburu,F. Legarda, C. Moreno, L. Sedano, TOWARDS STANDARDISATION OF TRITIUM DIFFUSION AND SOLUBILITY MEASUREMENTS IN FUSION REACTOR MATERIALS
  12. ↑ P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, LIBRETTO-4: Understanding and modeling tritium transport under irradiation, Fusion Engineering and Design 86 (2011) 2374–2377
  13. ↑ Modelat del transport de triti en un canal de l'embolcall regenerador de triti d'un reactor de fusió DT. PFC Pau Bermúdez García. Dec-2010
  14. ↑ P. Serret, S. Colominas, G. Reyes, J. Abellà, Characterization of ceramic materials for electrochemical hydrogen sensors,Fusion Engineering and Design 86 (2011) 2446–2449
  15. ↑ L. Llivina, S. Colominas, J. Abellà,Síntesis y caracterización de cerámicas para sensores de hidrógeno
  16. ↑ J.I. Linares, L.E. Herranz, B.Y. Moratilla, I.P. Serrano, Brayton Power Cycles For Electricity Generation From Fusion Reactors Jan. 2010, Volume 4, No.1 (Serial No.26) Journal of Energy and Power Engineering, ISSN 1934-8975, USA
  17. ↑ P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano, Tritiated Clouds Enviromental Impact in Air into the Western Mediterranean Basin Evaluation
  18. ↑ P. Castro, M. Velarde, J. Ardao, J. M. Perlado, L. Sedano,Consequences of Different Meteorological Scenarios in the Environmental Impact Assessment of Tritium Release ,Fusion Science and Technology / Volume 60 / Number 4 / November 2011 / Pages 1284-1287
  19. ↑ P. Martínez, N. Moral, L. Magielsen, A. Fedorov, C. Moreno, J.M. Perlado, L. Sedano, LIBRETTO-4: Understanding and modeling tritium transport under irradiation, Fusion Engineering and Design 86 (2011) 2374–2377
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