Viability of inert matrix fuel in reducing plutonium amounts in reactors

作者: Materials Section

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参考文章(112)
C. Ferguson, D.E. Lilly, S. Klima, C. Comfort, F. Rahnema, Thorium plutonium (TREX) fuel for weapons-grade plutonium disposition in pressurized water reactors Transactions of the American Nuclear Society. ,vol. 75, ,(1996)
Matthew Bunn, Management and disposition of excess weapons plutonium Transactions of the American Nuclear Society. ,vol. 71, ,(1994) , 10.1007/978-94-011-0996-3_8
J. P. Stora, Thermal conductivity of two-phase solid bodies. Nuclear Technology. ,vol. 17, pp. 225- 233 ,(1973) , 10.13182/NT73-A31266
Massimo Salvatores, Takehiko Mukaiyama, Lee Peddicord, Bruce Matthews, Pascal Baron, Alan Waltar, An Evaluation of the Proliferation Resistant Characteristics of Light Water Reactor Fuel with the Potential for Recycle in the United States ,(2004)
D. E. Peterson, M. E. Kassner, Phase diagrams of binary actinide alloys ASM International. ,(1995)
S. Pillon-Eymard, A. Languille, A. Mayorshin, V. Kisly, R. Thetford, L. Zaboudko, I. Kurina, T. Menshikova, B. Rogozkin, Status of Cea-Minatom collaborative experiment Bora-Bora: fuels with high plutonium content ,(2001)
Peter Hofmann, Siegfried J. L. Hagen, Gerhard Schanz, Alfred Skokan, Reactor Core Materials Interactions at Very High Temperatures Nuclear Technology. ,vol. 87, pp. 327- 333 ,(1989) , 10.13182/NT-TMI2-146
W.C. Thurber, F.R. McQuilkin, E.L. Jr. Long, M.F. Osborne, IRRADIATION TESTING OF FUEL FOR CORE B OF THE ENRICO FERMI FAST BREEDER REACTOR Oak Ridge National Laboratory. ,(1964) , 10.2172/4686227