Non-proliferating reprocessed nuclear fuels in pressurised water reactors: Fuel cycle options

Annals of Nuclear Energy

Volumn 25, Issue 12, 1998, Pages 937-962

  Pereira, Claubia ^a   Leite, Euzimar M ^a  

^a FEDERAL UNIVERSITY OF MINAS GERAIS   (Brazil)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0032143849     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(98)00008-5     Document Type: Article

References (29)

1. Galperin, A., Utilization of Light Water Reactors for Plutonium Incineration, American Nuclear Energy, Vol.22, 1995.
2. ANGRA-1/Cycle 3, Final Fuel Management Report, Relatório NUCLEN TS4/BN/1220/046/89.
3. Pinheiro, B., et al., Program of Research and Development on the Thorium Utilization in PWRs, NUCLEBRAS/CDTN 600/88, 1988.
4. Haas, D., Vandergheynst, A., Van Vliet, J., Lorenzelli, R., Nigon, J.-L., Mixed-Oxide Fuel Fabrication Technology and Experience at the Belgonucléaire and CFCa Plants and Further Developments for the MELOX Plant, Nuclear Technology, vol. 106, p. 60, April, 1994.
5. Vapirev ,E. I., Dimitrov, V. I., Jordanov, T. J., Ichristosko, V. D., Conversion of High Enriched Uranium in Thorium-232-Based Oxide Fuel for Light and Heavy Water Reactors: MOX-T Fuel, Nuclear Engineering and Design, Vol. 167, 1996.
6. Leite, E. M., Pereira, C., "Avaliação Neutrônica da Utilização de Tório na Composição de Combustíveis Reprocessados por Técnicas de Baixo Grau de Descontaminação", XI ENFIR, Agosto, 1997.
7. Eschbach, E.A., Some Plutonium Recycle Program Fuel Cycles Having Reduced Proliferation Characteristics, Nuclear Technology, vol. 41, p. 168, December, 1978.
8. Schlosser, G. J., Krebs, W-D, Urban, P., Experience in PWR and BWR Mixed-Oxide Fuel Management, Nuclear Technology, Vol. 102, April, 1993.
9. Clark, G., Uranium to 2010, Trans. Am. Nucl. Soc., vol. 70, p. 725, May, 1994.
10. MacLeod, H.M., YATES, G., Development of Mixed-Oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance, Nuclear Technology, vol. 102, p. 3, April, 1993
11. Duderstadt, J. J. et. al., Nuclear Reactor Analysis, John Wiley & Sons, 1976.
12. Asquith, J.G., Grantham, L.F., A Low-Decontamination Approach to a Proliferation-Resistant Fuel Cycle, Nuclear Technology, vol. 41, p. 137, December, 1978.
13. Steyn, J.J., In the Uranium Market the Only Certainty is Change, Nuclear Engineering International, p. 18, September, 1993.
14. Van Dievoet, J., Bairiot, H., Le Bastard, G., Pekarek, H., Roepenack, H., Mox fuel and its fabrication in Europe, Trans. Am. Nucl. Soc., vol. 61, p. 293, 1990.
15. Pobereskin, M., Kok, K. D., Madia, W. J., Coprocessing - An Evaluation of Chemical Reprocessing Without Plutonium Separation, Nuclear Technology, Vol. 41, December, 1981.
16. Rome, M., Salvatores, M., Mondot, J., Le Bars, M., Plutonium Reload Experience in French Pressurized Water Reactors, Nuclear Technology, vol. 94, p. 87, April, 1991.
17. Jahshan, N. S., Mcgeehan, T.J., An Evaluation of the Deployment of AIROX-Recycled Fuel in Pressurized Water Reactors, Nuclear technology, Vol. 106, June 1994.
18. ORIGEN2: (U,Pu) Fuel Cycle PWR & BWR Models, ORNL/TM-6051, September, 1978.
19. ORIGEN2: Alternative Fuel Cycle PWR Models, ORNL/TM-7005, February, 1980.
20. Taylor, P., Hocking, W. H., Johnson, L. H., Mceachern, R. J., Sunder, S. A., A Comparison of (Th,Pu)O2 and UO2 Fuel as Waste Forms for Direct Disposal, Nuclear Technology, Vol. 116, November, 1996.
21. Kuan, P., Carboneau, M.L., Jahshan, S.N., ORIGEN2 Calculations for AIROX-Recycled PWR Fuel, Trans. Am. Nucl. Soc., vol. 68, p. 93, 1993.
22. Cochran, R.G., Tsoulfanidis, N., The Nuclear Fuel Cycle: Analysis and Management, American Nuclear Society, 1990.
23. Cota, S., Pereira, C., "Estudos para a Utilização de Combustíveis Reprocessados por Técnicas de Baixo Grau de Descontaminação em Reatores PWR. Análise por Depleção, Revista Brasileira de Pesquisa e Desenvolvimento", Vol. 1, Agosto, 1996.
24. Cota, S., Pereira, C., Neutronic Evaluation of the Nonproliferation Reprocessed Nuclear Fuels in Pressurized Water Reactors, Annals of the Nuclear Energy, Vol. 24, N. 10, April, 1997.
25. Cota, S., "Estudo Neutrônico Prelímínar da Reciclagem de Combustíveis Alternatives em Reatores PWR", Dissertação para obtenção do título de mestre, DEN-UFMG, Fevereiro, 1996.
26. Güngör, S., Thorium Utilization in an Unmodified Pressurized Water Reactor, Annals of the Nuclear Energy, Vol. 17, N. 8, 1990.
27. Jahshan, S. N., AIROX Revisited-Neutronics Evaluation of Partially Decontaminated Reprocessed fuel, Trans. Am. Nucl. Soc., vol. 66, p. 522, 1992.
28. Cochran, T.B., Plutonium: The International Scene, Nuclear Energy, 35, No. 4, August, 211-222, 1996.
29. Wichers, V. A., Heijboer, R .J., INFCE Review, Part A: Introduction, Fuel Cycles and Technologies, ECN-I-93-001, June 1993.