Relevance of d-D interactions on neutron and tritium production in IFMIF-EVEDA accelerator prototype
Source abstract
Abstract
In the IFMIF-EVEDA accelerator prototype, deuterium is implanted in the components due to beam losses and in the beam dump, where the beam is stopped. The interaction of the deuterons with the deuterium previously implanted leads to the production of neutrons and tritium, which are important issues for radioprotection and safety analysis. A methodology to assess these production pathways in more realistic approach has been developed. The new tools and their main achievement are: (i) an “effective diffusivity coefficient” (deduced from available experimental data) that enables simulation of the diffusion phase, and (ii) the MCUNED code (able to handle deuteron transport libraries) allows to simulate the transport-slowdown of deuteron/tritium (to get the concentration profiles) and the neutron/tritium productions from d-Cu and d-D for up to 9 MeV incident deuteron. The results with/without theses tools are presented and their effect on the relevance of d-D sources versus d-Cu is evaluated.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear reactor physics and engineering · Nuclear Physics and Applications · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (22)
Show source-provided references
1. J.F. Ziegler, M.D. Ziegler, J.P. Biersack, SRIM 2008 Code. The Stopping and Range of Ions in Matter, 2008.
2. D.B. Pelowitz (Ed.), MCNPX User’s Manual, Version 2.5.0, LA-CP-05-0369 (2005). User’s Manual, Version 2.6.0, LA-CP-07-1473. J.S. Hendricks et al.: MCNPX 2.6.0 Extensions, LA-UR-08-2216 , 2008.
3. G.R. Longhurst, TMAP7: 1D, Transport of Tritium and Other Gas in Materials via Diffusion Model, Longhurst, INNEL. TMAP7 Users Manual, INEEL/EXT-04-02352, INNEL, 2004.
4. Niita · Radiat. Meas. · 2006 · 41 · 108010.1016/j.radmeas.2006.07.013 ↗
5. Sanz · Fusion Sci. Technol. · 2009 · 56 · 27310.13182/FST09-A8914 ↗
6. García · Nucl. Technol. · 2009 · 168 · 13210.13182/NT09-A9113 ↗
7. Jones · Nucl. Fusion · 2006 · 46 · 35210.1088/0029-5515/46/6/S17 ↗
8. Kim · Nucl. Instrum. Methods · 1977 · 145 · 910.1016/0029-554X(77)90553-5 ↗
9. Kim · Nucl. Technol. · 1979 · 44 · 31510.13182/NT79-A32265 ↗
10. B. Brañas et al., Prelimary design of IFMIF-EVEDA Beam Dump, Draft. April, 2009.
11. Fumelli · Sci. Instrum. · 1986 · 57 · 126610.1063/1.1138640 ↗
12. F. Reiter, K.S. Forcey, G. Gervasini, A compilation of tritium–material interaction parameters in fusion reactor materials. Joint Research Centre. ISPRA Site Institute for Safety Technology. Commission of the European Communities. EUR 15217EN, 1993.
13. T.J. Dolan, R.A. Anderl, Assessment of Database for Interaction of Tritium with ITER Plasma Facing Materials. EGG-FSP-11348 ITER/93/US/TUSA=lO, 1994.10.2172/10191406 ↗
14. Fukui · J. Nucl. Mater. · 1995 · 220–222 · 81010.1016/0022-3115(94)00589-3 ↗
15. Panigrahi · Bull. Mater. Sci. · 1996 · 19 · 6110.1007/BF02744788 ↗
16. Anderl · J. Nucl. Mater. · 1999 · 266–269 · 76110.1016/S0022-3115(98)00878-2 ↗
17. V. Blideanu, M. Garcia, Ph. Joyer, D. Lopez, A. Mayoral, F. Ogando, J. Sanz, P. Sauvan, Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF, in: Proceedings, Sapporo (Japan), 7–12 September, 2009.
18. Sauvan · Nucl. Inst. Methods Phys. Res., A · 2010 · 614 · 32310.1016/j.nima.2009.12.084 ↗
19. Chadwick · Nucl. Data Sheets · 2006 · 107 · 293110.1016/j.nds.2006.11.001 ↗
20. A.J. Koning, D. Rochman, Consistent Talys-based Evaluated Nuclear Data Library including covariance data (TENDL2008 ).
21. A.J. Koning, S. Hilaire, M.C. DUujvestijn, “TALYS-1.0”, in: Proc. of the Int. Conference on Nuclear Data for Science and Technology – ND2007, April 22–27, 2007 Nice France editors O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, S. Leray (Eds.), EDP Sciences, 2008, pp. 211–214.10.1051/ndata:07767 ↗
22. United Stated Nuclear Regulatory Commission recommendations. (USNRC Table XXX4) .