Rejuvenation of light water reactor spent fuel in fusion blankets

Annals of Nuclear Energy

Volumn 25, Issue 16, 1998, Pages 1317-1339

  Şahin, Sümer ^a   Yapici, Hüseyin ^b  

^a Gazi Hospital   (Turkey)

^b ERCIYES UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0032210824     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(98)00018-8     Document Type: Article

References (55)

1. Al-Kusayer, T. A., Şahin, S. and Drira, A. (1988) CLAW-IV coupled 30 neutrons, 12 gamma-ray group cross sections with retrieval programs for radiation transport calculations. Radiation Shielding Information Center, Newsletter, Oak Ridge National Laboratory, May, 4.
2. Arthur, E. D. (1991) A new concept for accelerator driven transmutation of nuclear wastes. Fusion Technology 20, 641.
3. Barrett, J. and MacFarlane, R. E. (1979) CLAW, Coupled 30 neutrons, 12 gamma-ray group cross sections for neutron transport calculations. LA-7808-MS, Los Alamos Scientific Laboratory.
4. Basov, N. G., Belousov, N. I., Grishunin, P. A., Kharitonov, V. V., Rozanov, V. B. and Subbotin, V. I. (1992) Transmutation of high-level fission products and activities in a laser-driven fusion reactor. Fusion Technology 22, 350,
5. Berwald, D. H. and Duderstadt, J. J. (1979) Preliminary design and neutronic analysis of a laser fusion driven actinide waste burning hybrid reactor. Nuclear Technology 42, 34.
6. Blink, J. A., Hogan, W. J., Hovingh, J., Meier, W. R. and Pitts, J. H. (1985) High-yield lithium-injection fusion-energy (HYLIFE) reactor. UCRL-53559, Lawrence Livermore National Laboratory.
7. Cappiello, M. W., Rider, W. J. and Iveland, J. R. (1991) Target/blanket conceptual designs for the Los Alamos accelerator transmutation of nuclear waste (ATW) concept. Fusion Technology 20, 648.
8. Doncals, R. A., Paik, N. C , Varner, S. K., Rathbun, R. W. and Petras, D. S. (1979) Nonrefueling liquid-metal fast breeder reactor. Transactions, American Nuclear Society 33, 445.
9. Engle Jr, W. W. (1970) ANISN, a one-dimensional discrete ordinates transport code with anisotropic scattering. K1693, Oak Ridge National Laboratory.
10. Erickson, K., McCormick, N. Y. and Woodruff, G. L. (1981) Power density flattening in fusion-fission hybrid reactors. Nuclear Technology/Fusion 1, 533.
11. Greenspan, E. (1984) Fusion-fission hybrid reactors. Advances in Science and Technology 16, 289.
12. Greenspan, E., Misulovin, A. and Gilal, D. (1983) Power density flattening in fusion-fission hybrid reactors. Nuclear Technology/Fusion 3, 485.
13. Heising-Goodman, C. D. (1979) Qualifying the relative diversion resistance and economics of alternative fuel cycles. Transactions, American Nuclear Society 33, 446.
14. Jaeger, R. G., Blizard, E. P., Chilton, A. B., Grotenhuis, M., Hönig, A., Jaeger, Th. A. and Eisenlohr, H.H. (eds) (1968) Shielding Fundamentals and Methods, Engineering Compendium on Radiation Shielding, I. Springer-Verlag, Berlin.
15. 233U produced in a fusion reactor blanket. Journal of Fusion Energy 5, 245.
16. Konaski, K., Sasao, N., Louvet, P., Sato, I. and Hirao, Y. (1991) New transmutation method by using moving target. Fusion Technology 20, 664.
17. Ledergerber, G., Ingold, F., Stratton, R. W., Alder, H.-P., Prunier, C., Warin, D. and Bauer, M. (1996) Preparation of transuranium fuel and target materials for transmutation of actinide's by gel coconversion. Nuclear Technology 114, 194.
18. 3Si blanket. In Proceedings, 3rd Topical Meeting on Technology of Controlled Nuclear Fusion, Santa Fe, New Mexico, May 9-11, 1978. CONF-780508 1, 219.
19. Lee, J. D. (1994) Waste disposal assessment of HYLIFE-II structure. Fusion Technology 26, 74.
20. Leggertt, D. and Omberg, R. P. (1987) Mixed oxide fuel development. In Proceedings International Conference on Fast Breeder Systems: Experience Gained and Path to Economical Power Generation. American Nuclear Society, Richland, WA.
21. MacFarlane, R. E. (1993) TRANSX-2, a code for interfacing MATXS cross-section libraries to nuclear transport codes, Internal Report, LANL.
22. Meyer, W., Loyalka, S. K., Nelson, W. E. and Williams, R. W. (1977) The homemade nuclear bomb syndrome. Nuclear Safety 18, 427.
23. Moir, W. R., Bieri, R. L., Chen, X. M., Dolan, T. J., Hoffman, M. A., House, P. A., Leber, R. L., Lee, J. D., Lee, Y. T., Liu, J. C., Longhurst, G. R., Meier, W. R., Peterson, P. F., Petzoldt, R. W., Schrock, V. E., Tobin, M. T. and Williams, W. H. (1994) HYLIFE-II a molten-salt inertial fusion energy power plant design-final report. Fusion Technology 25, 5.
24. Mynatt, F. R. (1977) Analysis of acceleration breeder concepts with LMFBR, GCFF and molten salt type blankets. In Proceedings Information Meeting on Accelerator Breeding. Upton, New York.
25. Perlado, M. Guinan, M. W. and Abe, K. (1995) Radiation damage in structural materials, In Energy from Inertial Fusion, International Atomic Energy Agency, 272, Vienna.
26. Prunier, C., Boussard, F., Koch, L. and Coquerelle, M. (1997) Some specific aspects of homogeneous americium-and neptunium-based fuels transmutation through the outcomes of the superfact experiment in phoenix fast reactor. Nuclear Technology 119, 141.
27. Şahin, S. (1980) Reply to the remarks on the plutonium-240 induced preignition problem in a nuclear device. Nuclear Technology 54, 431.
28. Şahin, S. (1981) Neutronic analysis of fast hybrid thermionic reactors. Atomkernenergie/ Kerntechnik 39, 41.
29. Şahin, S. (1982) Addendum. Nuclear Technology 58, 354.
30. Şahin, S. (1990) Power flattening in a catalysed deuterium-deuterium fusion driven hybrid blanket using nuclear waste actinide's. Nuclear Technology 92, 93.
31. Şahin, S. and Al-Eshaikh, M. (1986) A numerical-graphical power flattening method for fast hybrid blanketIn Proceedings, 4th International Conference on Emerging Nuclear Energy Systems, Madrid, Spain, 59.
32. Şahin, S. and Al-Eshaikh, M. (1987) Fission power flattening in hybrid reactors using mixed fuel. Fusion Technology 12, 395.
33. Şahin, S. and Al-Kusayer, T. A. (1983) Nuclear waste actinides as fissile fuel in hybrid blankets. 6th Miami International Conference on Alternative Energy Sources, Proceedings of the Extended Abstracts, 350-353, Miami Beach, FL.
34. 2 blanket with (D,D) driver. Atomkernenergie/Kerntechnik 47, 259-266.
35. 2 hybrid blanket driven by a (deuterium-tritium) source. Fusion Technology 10, 1297.
36. Şahin, S. and Calinon, R. (1985) Criticality of curium, assemblies. Atomkernenergie/Kerntechnik 46, 45.
37. Şahin, S. and Kumar, A. (1984) Fast hybrid thermionic blankets with actinide waste fuel. Nuclear Technology/Fusion 5, 374.
38. Şahin, S. and Ligou, J. (1980) The effect of the spontaneous fission of plutonium-240 on the energy release in a nuclear explosive. Nuclear Technology 50, 88.
39. Şahin, S. and Yapici, H. (1989a) Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel. Fusion Technology 16, 331.
40. Şahin, S. and Yapici, H. (1989b) Rejuvenation of CANDU spent fuel in a hybrid blanket. Transactions, American Nuclear Society 59, 105.
41. Şahin, S., Al-Kusayer, T. A. and Raoof, M. A. (1986) Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver. Fusion Technology 10, 84.
42. Şabin, S., Erişen, A. and Çebi, Y. (1987) A fast hybrid blanket with flat fusion power over a long operational period. Transactions, American Nuclear Society 54, 134.
43. Şabin, S., Erişen, A. and Çebi, Y. (1989) Realization of a flat fission power density in a hybrid blanket over long operation periods. Fusion Technology 15, 37.
44. Şahin, S., Yapici, H. and Baltaciôǧlu, E. (1989) Heavy water reactor spent fuel regeneration with fusion neutrons. Transactions, American Nuclear Society 60, 176.
45. Şahin, S., Baltacioǧlu, E. and Yapici, H. (1991) Potential of a catalysed fusion driven hybrid reactor for the regeneration of CANDU spent fuel. Fusion Technology 20, 26.
46. Şahin, S., Moir, R. W., Şahinaslan, A. and Şahin, H. M. (1996) Radiation damage in liquid protected first wall materials for IFE-reactors. Fusion Technology 30, 1027.
47. Şahin, S., Şahinaslan, A. and Kaya, M. (1998) MFE-reactors with liquid protection for the first-wall, submitted to Fusion Technology.
48. Şahin, S., Moir, R. and Ünalan, S. (1994) Neutronic investigation of a power plant using peaceful nuclear explosives. Fusion Technology 26, 1311-1325.
49. Şahin, S., Şahinaslan, A. and Kaya, M. (1998) MFE-reactors with liquid protection for the first-wall, Fusion Technology, to be published in September 1998.
50. Smith, D. L. et al. (1984) Blanket comparison and selection study-final report. ANL/ FPP-84-1, Argonne National Laboratory.
51. Takada, H., Takizuka, T., Kanno, L, Nishida, T., Akabori, M. and Kaneko, Y. (1991) A concept of actinide transmutation with intense proton accelerator. Fusion Technology 20, 673.
52. Takahashi, H. (1991) A fast breeder and incinerator assisted by a proton accelerator. Fusion Technology 20, 657.
53. Takahashi, H., Powell, J. and Kouts, H. (1984) Accelerator breeder with uranium and thorium target. Atomkernenergie/Kerntechnik 44, 181.
54. Todosow, M., Ludewig, H., Takahashi, H. and Powell, J. (1991) High flux particle bed reactor systems for rapid transmutation of actinides and long lived fission products. Fusion Technology 20, 678.
55. Waltar, E. and Deitrich, L. W. (1988) Status of research on key LMR safety issues. Nuclear Safety 29, 125.