Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel

Annals of Nuclear Energy

Volumn 28, Issue 3, 2001, Pages 203-223

  Şahin, Sümer ^a   Özceyhan, Veysel ^b   Yapici, Hüseyin ^c  

^a GAZI UNIVERSITY   (Turkey)

^b ERCIYES UNIVERSITY   (Turkey)

^c NIGDE UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; FUSION REACTORS; HEAT TRANSFER; MIXED OXIDE FUELS; NEUTRON SOURCES; PLUTONIUM; RADIOISOTOPES; SPENT FUELS; THORIA; URANIUM DIOXIDE;

CUMULATIVE FISSILE FUEL ENRICHMENT (CFFE); TRIPLE MIXED OXIDE (TMOX) FUEL;

BREEDER REACTORS;

EID: 0035254619     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(00)00047-5     Document Type: Article

References (42)

1. AECL, 1979. Data Base for a CANDU-PHWR Operating on a Once-Through Natural Uranium Cycle (AECL-6593). Atomic Energy of Canada Limited.
2. Al-Kusayer, T.A., Şahin, S., Drira, A., 1988. CLAW-IV, coupled 30 neutrons, 12 gamma ray group cross sections with retrieval programs for radiation transport calculations. RSIC Newsletter, Radiation Shielding Information Center, Oak Ridge National Laboratory, p. 4.
3. Barrett, R.J., 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. Berwald, D.H., Maniscalco, J.A., Lee, J.D., Moir, R.W., 1980. Fission suppressed tandem mirror hybrid reactor options. In: Proceedings of the Fourth Topical Meeting on the Technology of Controlled Nuclear Fusion. King of Prussia, PA, 14-17 October 1980, p. 1465.
5. Berwald D.H., Whitley R.H., Garner J.K.et al. Updated Reference Design of a Liquid Metal Cooled Tandem Mirror Fusion Breeder. Fusion Technology. 12:1987;30.
6. Bondarenko I.I. Group Constants for Nuclear Reactor Calculations. 1964;Consultants Bureau, New York.
7. Brooks G.L. Advances in commercial heavy water reactor power stations. Trans. Am. Nucl. Soc. 56:1988;41.
8. Engle, W.W., 1970. ANISN, a One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering (K1693), Oak Ridge National Laboratory.
9. Greenspan, E., 1984. Fusion-fission hybrid reactors. In: Lewins, J., Becker, M. (Eds.), Advances in Science and Technology, Vol. 16. Plenum Press, p. 298.
10. Jaeger R.G.et al. Engineering Compendium on Radiation Shielding, Vol. I, Shielding Fundamentals and Methods. 1968;Springer Verlag, Berlin.
11. Jassby D.L., Berwald D.H., Garner J.K.et al. Fast-fission tokamak breeder reactors. Fusion Energy. 5:1986;171.
12. IAEA, 1979. Status and Prospects of Thermal Breeders and their Effects on Fuel Utilization. Technical Report Series No. 195, International Atomic Energy Agency.
13. Kumar A., Şahin S. Investigation of neutronics of some (D,T) driven experimental thorium hybrid blankets with actinide multipliers. Journal of Fusion Energy. 3:1983;185.
14. Lee J.D. Waste disposal assessment of HYLIFE-II structure. Fusion Technology. 26:1994;74.
15. Leggert, R.D., Omberg, R.P., 1987. Mixed oxide fuel development. In: Proc. Int. Conf. Fast Breeder Systems: Experience Gained and Path to Economical Power Generation, Richland, WA, 13-17 September, American Nuclear Society.
16. MacFarlane, R.E., 1993. TRANSX-2, A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes. Los Alamos Scientific Laboratory.
17. Maniscalco J.A., Berwald D.H., Moir R.W., Lee J.D., Teller E. The fusion breeder - an early application of nuclear fusion. Fusion Technology. 6:1984;584.
18. Meyer W., Loyalka S.K., Nelson W.E., Williams R.W. The homemade nuclear bomb syndrome. Nuclear Safety. 18:1977;427.
19. Moir, R.W., 1982. The fusion breeder (UCRL-87290). Submitted to the National Science Foundation Policy Workshop, Washington, DC, 4-5 March. Lawrence Livermore Laboratory, Livermore, CA.
20. Moir R.W. Fissile fuel from fusion. In: Energy and Technology Review (UCRL-52000-85-1). 1985;Lawrence Livermore National Laboratory, Livermore,CA.
21. Moir R.W., Lee J.D. Helium-cooled, Flibe-breeder, beryllium-multiplier blanket for minimars. Fusion Technology. 10:1986;619.
22. Moir R.W., Lee J.D., Fulton F.J.et al. Helium-Cooled Molten Salt Fusion Breeder (UCID-20153). 1984;Lawrence Livermore National Laboratory, Livermore, CA.
23. Moir R.W., Lee J.D., Neef W.S.et al. Feasibility Study of a Fission-Suppressed Tokamak Fusion Breeder (UCID-20154). 1984;Lawrence Livermore National Laboratory, Livermore, CA.
24. Moir R.W., Lee J.D., Maninger R.C.et al. Helium-cooled, flibe breeder, beryllium multiplier blanket. Fusion Technology. 8:1985;133.
25. Moir R.W., Lee J.D., Fulton F.J.et al. Design of a helium-cooled molten salt fusion breeder. Fusion Technology. 8/1(2A):1985;465.
26. Şahin S. Reply to the remarks on the plutonium-240 induced preignition problem in a nuclear device. Nuclear Technology. 54(3):1980;431.
27. Şahin S. Addendum. Nuclear Technology. 58:1982;354.
28. Şahin S. Power flattening in a hybrid blanket using nuclear waste actinides. Kerntechnik. 53:1989;285.
29. Şahin, S., Al-Eshaikh, M., 1987a. A numerical-graphical power flattening method for source driven fast fission blankets. In: Proceedings of the 4th Int. Conference on Emerging Nuclear Energy Systems, Madrid, Spain, 30 June-4 July 1986. World Scientific Publishing Company, p. 59.
30. Sahin S., Al-Eshaikh M. Fission power flattening in hybrid blankets using mixed fuel. Fusion Technology. 12:1987;315.
31. 2 blanket with (D,D) driver. Atomkernenergie/Kerntechnik. 47:1985;259.
32. 2 hybrid blanket driven by a (deuterium-tritium) source. Fusion Technology. 10:1986;1297.
33. Şahin S., Ligou J. The effect of the spontaneous fission of plutonium-240 on the energy release in a nuclear explosive. Nuclear Technology. 50(1):1980;88.
34. Şahin S., Yapici H. Neutronic analysis of a thorium fusion breeder with enhanced protection againts nuclear weapon proliferation. Annals of Nuclear Energy. 26(1):1998;13.
35. Şahin, S., Al-Kusayer, T.A., Abdul-Raoof M., 1985. Neutronic performance of (deuterium-deuterium) driven experimental thorium hybrid blankets. Transactions of the American Nuclear Society 1985 Annual Meeting, Vol. 49, Boston, p. 102.
36. Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver. Fusion Technology. 10:1986;84.
37. Şahin S., Yapici H., Baltacoglu E., Al-Kusayer T.A. A hybrid reactor design concept driven by cold (D,T) fusion neutrons and fueled with metallic thorium. International Journal of Energy-Environment-Economics. 1:1991;167.
38. Şahin S., Baltacioglu E., Yapici H. Potential of a catalysed fusion driven hybrid reactor for the regeneration of CANDU spent fuel. Fusion Technology. 20:1991;26.
39. Şahin S., Moir R., Unalan S. Neutronic investigation of a power plant using peaceful nuclear explosives. Fusion Technology. 26(4):1994;1311.
40. Şahin S., Moir R.W., Şahinaslan A., Şahin H.M. Radiation damage in liquid-protected first wall materials for IFE-reactors. Fusion Technology. 30(3):1996;1027.
41. Sahin S., Sahinaslan A., Kaya M. Neutronic calculations for a magnetic fusion energy reactor with liquid protection for the first-wall. Fusion Technology. 34(2):1998;95.
42. Waltar A.E., Deitrich L.W. Status of research on key LMR safety issues. Nuclear Safety. 29(2):1988;125.