On the radiation damage characterization of candidate first wall materials in a fusion reactor using various molten salts
Source abstract
Abstract
Evaluating radiation damage characteristics of structural materials considered to be used in fusion reactors is very crucial. In fusion reactors, the highest material damage occurs in the first wall because it will be exposed to the highest neutron, gamma ray and charged particle currents produced in the fusion chamber. This damage reduces the lifetime of the first wall material and leads to frequent replacement of this material during the reactor operation period. In order to decrease operational cost of a fusion reactor, lifetime of the first wall material should be extended to reactor's lifetime. Using a protective flowing liquid wall between the plasma and first wall can decrease the radiation damage on first wall and extend its lifetime to the reactor's lifetime. In this study, radiation damage characterization of various low activation materials used as first wall material in a magnetic fusion reactor blanket using a liquid wall was made. Various coolants (Flibe, Flibe + 4% mol ThF4, Flibe + 8% mol ThF4, Li20Sn80) were used to investigate their effect on the radiation damage of first wall materials. Calculations were carried out by using the code Scale4.3 to solve Boltzmann neutron transport equation. Numerical results brought out that the ferritic steel with Flibe based coolants showed the best performance with respect to radiation damage. (c) 2006 Elsevier B.V. All rights reserved.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. M.A. Abdou, On the exploration of innovative concepts for fusion chamber technology, APEX Interim Report (Overview), UCLA-ENG-99-206, UCLA-FNT-107, University of California, Los Angeles, California, 1999.
2. Van der Schaaf · Fusion Eng. Des. · 2000 · 51&52 · 4310.1016/S0920-3796(00)00318-5 ↗
3. Dyomina · J. Nucl. Mater. · 1998 · 258–263 · 178410.1016/S0022-3115(98)00133-0 ↗
4. Kazakov · J. Nucl. Mater. · 1998 · 258–263 · 145810.1016/S0022-3115(98)00328-6 ↗
5. Jones · J. Nucl. Mater. · 1999 · 271& 272 · 51810.1016/S0022-3115(98)00864-2 ↗
6. Solonin · J. Nucl. Mater. · 2000 · 283–287 · 146810.1016/S0022-3115(00)00350-0 ↗
7. Klueh · J. Nucl. Mater. · 2000 · 280 · 35310.1016/S0022-3115(00)00060-X ↗
8. Klueh · J. Nucl. Mater. · 1995 · 227 · 1110.1016/0022-3115(95)00143-3 ↗
9. Abdou · Fusion Eng. Des. · 1999 · 45 · 14510.1016/S0920-3796(99)00018-6 ↗
10. Kurtz · J. Nucl. Mater. · 2000 · 283–287 · 7010.1016/S0022-3115(00)00351-2 ↗
11. Smith · Int. J. Ref. Metals Hard Metals · 2000 · 18 · 21310.1016/S0263-4368(00)00037-8 ↗
12. Xu · Int. J. Ref. Metals Hard Metals · 2000 · 18 · 23110.1016/S0263-4368(00)00038-X ↗
13. H.M. Chung, B.A. Loomis, D.L. Smith, Development and testing of vanadium alloys for fusion applications 239 (1996) 139–156.
14. Zinkle · Fusion Eng. Des. · 2000 · 51&52 · 5510.1016/S0920-3796(00)00320-3 ↗
15. Kohyama · J. Nucl. Mater. · 2000 · 283–287 · 2010.1016/S0022-3115(00)00156-2 ↗
16. Hasegawa · J. Nucl. Mater. · 2000 · 283–287 · 12810.1016/S0022-3115(00)00374-3 ↗
17. Jones · J. Nucl. Mater. · 1995 · 219 · 5510.1016/0022-3115(94)00390-4 ↗
18. Riccardi · Fusion Eng. Des. · 2000 · 51&52 · 1110.1016/S0920-3796(00)00311-2 ↗
19. Seki · J. Nucl. Mater. · 1998 · 258–263 · 179110.1016/S0022-3115(98)00137-8 ↗
20. Aiello · Fusion Eng. Des. · 2000 · 51–52 · 7310.1016/S0920-3796(00)00376-8 ↗
21. Übeyli · J. Fusion Energ. · 2004 · 23 · 18310.1007/s10894-005-5598-8 ↗
22. Şahin · Energy Convers. Manage. · 2005 · 46 · 318510.1016/j.enconman.2005.03.007 ↗
23. Moir · Nucl. Fusion · 1997 · 37 · 55710.1088/0029-5515/37/4/I13 ↗
24. Christofilos · J. Fusion Energ. · 1989 · 8 · 9710.1007/BF01050784 ↗
25. Şahin · Fusion Technol. · 1996 · 30 · 102710.13182/FST96-A11963072 ↗
26. Moir · Fusion Technol. · 1994 · 25 · 510.1016/0920-3796(94)90049-3 ↗
27. Tobin · Fusion Technol. · 1991 · 19 · 76310.13182/FST91-A29437 ↗
28. Lee · Fusion Technol. · 1994 · 26 · 7410.13182/FST94-A30301 ↗
29. Radiation Damage in Structural Materials
30. Şahin · Fusion Technol. · 1998 · 34 · 9510.13182/FST98-A56 ↗
31. Şahin · The Arab. J. Sci. Eng. · 2002 · 27 · 173
32. S. Şahin, A. Şahinaslan, M. Kaya, M., S. Yılmaz, Radiation damage in liquid-protected first wall materials for MFE-reactors, Transactions of the American Nuclear Society 1997 Winter Meeting, 77, pp. 158, (1997) Albuquerque.
33. Şahin · Energ. Convers. Manage. · 2004 · 45 · 149710.1016/j.enconman.2003.09.014 ↗
34. Youssef · Fusion Eng. Des. · 2000 · 49&50 · 71910.1016/S0920-3796(00)00179-4 ↗
35. Abdou · Fusion Eng. Des. · 2001 · 54 · 18110.1016/S0920-3796(00)00433-6 ↗
36. A. Ying, et al., Thick liquid blanket concept. APEX Interim Report, UCLA-ENG-99-206, UCLA-FNT-107, University of California, (1999) Los Angeles, USA.
37. W.C. Jordan, S.M. Bowman, ‘Scale Cross-Section Libraries’, NUREG/CR-0200, Revision 5, 3, section M4, ORNL/NUREG/CSD-2/V3/R5, Oak Ridge National Laboratory (1997).
38. N.M. Greene, L.M. Petrie, ‘XSDRNPM, A One-Dimensional Discrete-Ordinates Code for Transport Analysis’, NUREG/CR-0200, Revision 5, 2, Section F3, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997).
39. S. Şahin, Radiation Shielding Calculations for Fast Reactors (in Turkish), Gazi University, Publication # 169, Faculty of Science and Literature, Publication number 22, (1991) Ankara, Turkey.
40. N.M. Greene, ‘BONAMI, Resonance Self-Shielding by the Bondarenko Method’, NUREG/CR-0200, Revision 5, 2, section F1, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997).
41. N.M. Greene, L.M. Petrie, R.M. Westfall, ‘NITAWL-II, Scale System Module For Performing Resonance Shielding and Working Library Production’, NUREG/CR-0200, Revision 5, 2, Section F2, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997).
42. N.F. Landers, L.M. Petrie, ‘CSAS, Control Module for Enhanced Criticality Safety Analysis Sequences’, NUREG/CR-0200, Revision 5, 1, Section C4, ORNL/NUREG/CSD-2/V1/R5, Oak Ridge National Laboratory (1997).
43. Yapıcı, H., XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data, Erciyes University, (2001) Kayseri, Turkey.
44. Duderstadt · 1982
45. A. Blink, et al., High-yield lithium-injection fusion energy (HYLIFE) reactor, UCRL-53559, in: K.L. Essary, K.E. Lewis (Eds.), Lawrence Livermore National Laboratory (1985) USA, 1985.10.2172/6124368 ↗