Hacı Mehmet ŞAHİN, Kadir YILDIZ, Taner ALTINOK, Yusuf KILIÇ

Bir toryum füzyon- fisyon reaktöründe nükleer atıkların farklı soğutucularla değerlendirilmesi

Bu çalışmada 14.1 MeV füzyon nötron kaynaklı ve $ThO_2$ yakıtlı bir hibrid reaktörde 48 aylık çalışma süresince Np, Am ve Cm gibi nükleer atıkların değerlendirilmesinin farklı soğutucularla nötronik analizi yapılmıştır. Soğutucu olarak flibe, tabii lityum ve gaz soğutucu seçilmiştir. Flibe soğutuculu manto diğer soğutuculara nazaran başlangıçtaki $^{237}Np$ miktarının % 49.83'ünü tüketerek 48. ayda en iyi sonucu vermiştir.Önemli bir nükleer atık olan $^{241}Am$ ve $^{243}Am$ çekirdekleri reaktör işlem zamanı boyunca hibrid manto içinde azalmakta ve özellikle flibe ve gaz soğutuculu mantolarda tabii lityum soğutuculu mantoya göre daha fazla tüketilmektedir. 48 ay sonunda $^{241}Am$ ve $^{243}Am$ çekirdekleri flibe soğutuculu mantoda sırasıyla % 51.68 ve % 44.32 oranında tüketilmektedir.$^{244}Cm$ tüketiminin bir kısmı çok kıymetli bir nükleer yakıt olan $^{245}Cm$ üretimini sağlamaktadır. 48 aylık işlem periyodu sonunda en fazla $^{245}Cm$ miktarı 1.27 kg/m ile flibe soğutuculu mantoda görülmektedir.

An evalution of nuclear waste in a thorium fusion-fission reactor with different moderators

In this work, a neutronic anlysis and an evaluation of the nuclear waste such as Np, Am, Cm has been performed for a hybrid reactor with different moderators used $ThO_2$ as fuel and fusion neutron drivers with 14.1MeV as neutron source. Flibe, natural lithium and gas were selected as coolant in hybrid blankets. Flibe moderated blanket spent amount of $^{243}Am$ with 49.83 % according to the start at the end of 48th months and it gave well result. Amount of $^{241}Am$ and $^{243}Am$, important nuclear waste, have decreased in hybrid blanket during reactor operation time. They are spent in especially flibe and gas moderated blankets more than natural lithium moderated blanket. At the end of 48th months, $^{241}Am$ and $^{243}Am$ were consumed in ratio of 51,68 % and 44,32 % in flibe moderated blanket. The portion of the consumption of $^{244}Cm$ produces $^{245}Cm$, which is very precious nuclear fuel. It was shown that flibe moderated blanket has produced amount of $^{245}Cm$ with 1,27 kg/m more than the other blankets during 48th months operation time.

___

1. Ünak, T., What is the Potential Use of Thorium in the Future Energy Production Technology? Progress in Nuclear Energy, Vol. 37, No. 1-4, pp. 137-144, (2000)
2. Manşon, B., Thomas, H. P. and Hans W. L., Nuclear Chemical Engineering, McGraw-Hill Book Company, (1981)
3. Mynatt, F.R., Analysis of Acceleration Breeder Concepts with LMFBR, GCFF and Molten Salt Type Blankets, Proc. Information Mtg. Accelerator Breeding, Upton, January 18-19, New York (1977).
4. Blinkin, L.V. and Novikov, M.Y., Optimal Symbiotic Molten Salt Fission-Fusion System, Kurchatöv Institute of Atomic Energy, 1 AE- 2819, Moscow, UCRL-Trans-11288 (1977).
5. Moir, R.W. (editor), Tandem Mirror Hybrid Reactor Design Study Annual Report, UCRL- 52875, Lawrence Livermore Laboratory (1979).
6. Ragheb, M.H., et al., Nuclear Performance of Molten Salt Fusion-Fission Symbiotic Systems for Catalyzed DD and DT Reactors, ORNLTM- 6560, OAK Ridge National Laboratory (1979).
7. Teller, E., Fusion, Magnetic Confinement, Vol. 1, Part B, Academic Press (1981).
8. Berwald, D.H., et al., Fission Suppressed Hybrid Reactor-the Fusion Breeder, UCID- 19638, Lawrence Livermore Laboratory (1982).
9. Lee, D.J. et al., Feasibility Study of a Fission- Suppressed Tandem-Mirror Hybrid Reactor, UCID-19327, Lawrence Livermore National Laboratory (1982).
10. Greenspan, E., Fusion-Fission Hybrid Reactors, Advances in Science and Technology, Vol. 16, p. 289, J. LEWINS and M. BECKER, Eds., Plenum Press (1984).
11. Moir, R. W. et al., Helium-Cooled, Flibe Breeder, Beryllium Multiplier Blanket, Fusion Technology, Vol. 8, p. 133 (1985)
12. Moir, R. W. and Lee, J. D., Helium-Cooled , FLiBe-Breeder, Beryllium-Multiplier Blanket for Minimars, Fusion Technology, Vol. 10, p. 619(1986)
13. Seelmann- Eggebert, W., Pfenning, G., Münzel, H., Klewe-Nebenius, H., Chart of the Nuclides, Kernforschungszentrum Karlsruhe GmbH, Institut für Radiochemie, (1981).
14. "Information on nuclear energy for electricity, and uranium for it",Uranium Information Centre (http://www.uic.com.au), Melbourne, Australia.
15. Wilson D. J., The Use of Thorium as an Alternative Nuclear Fuel, Australian Atomic Energy Commission, Research Establishment, (1992)
16. Şahin, S. and T. Al-Kusayer, $^{244}Cm$ as Multiplier and Breeder in a ThO2 Hybrid Blanket Driven by a (Deuterium-Tritium) Source, Fusion Technology, Vol. 10, p. 1297 (1986)
17. Şahin, S.: "Power Flattening in a Catalyzed (D,D) Fusion Driven Hybrid Blanket Using Nuclear Waste Actinides", Nuclear Technology, Vol. 92, pp. 93-105 (1990)
18. Şahin, S., H. Yapıcı and E. Baltacıoğlu, "Regeneration of LWR Spent Fuel in Hybrid Reactors," Kerntechnik. Vol. 59, No. 6, p. 270 (1994).
19. Şahin, S., H. Yapıcı, "Neutronic Analysis of a Thorium Fusion Breeder with Enhanced Protection Againts Nuclear Weapon Proliferation", Annals of Nuclear Energy, Vol. 26, no. 1,p. 13(1998)
20. Lee, D.J., Waste Disposal Assessment of HYLIFE-II structure, Fusion Technology, Vol. 26, p. 74(1994).
21. Şahin, S., R. W. Moir and S. Ünalan: "Neutronic Investigation of a Power Plant Using Peaceful Nuclear Explosives", Fusion Technology, Vol. 26, No. 4, p. 1311 (1994).
22. Greene N. M., L. M. Petrie, (1997). "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.
23. Jordan W. C., S. M. Bowman , (1997). "Scale Cross-Section Libraries", NUREG/CR-0200, Revision 5, 3, section M4, ORNL/NUREG/CSD-2/V3/R5, Oak Ridge National Laboratory.
24. Şahin, S., "Comparison of Diffusion and Transport Theory for Fast Reactor Shielding Calculations," Atomkernenergie, Vol. 22, p. 24 (1973), also presented in extended form as Habilitation Thesis (in Turkish) to the Faculty of Science, University of Ankara, Turkey (1973).
25. Şahin, S., E. Baltacıoğlu and H. Yapıcı "Potential of a Catalyzed Fusion Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel," Fusion Technology, Vol. 20, p. 26(1991).
26. Şahin, S., H. Yapıcı and M. Bayrak, "Spent Mixed Oxide Fuel Rejuvenation in Fusion Breeders", Fusion Engineering and Design, Vol. 47, pp. 9-23(1999).
27. Şahin, S., H. Yapıcı and N. Şahin, "Neutronic Performance of Proliferation Hardened Thorium Fusion Breeders", Fusion Engineering and Design, Vol. 54, no. 1, pp. 63-77, (2000).