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- W3141535823 abstract "The reactor described employs a fuel system comprising a critical mass of U nitride fuel in contact with a non-critical solution of fissile metal in a molten metal solvent of low neutron absorption cross section. The fuel system is contained in an inert refractory- reactor vessel under a N/ sub 2/ atmosphere. The molten metal solvent consists of Sn, and graphite is employed for the reactor vessel. The non-critical solution is present in an amount sufficient to dissolve metal fission products, while precipitating from solution an amount of nitride substantially equal to that lost by fission. The N/sub 2/ atmosphere is maintained under pressure and temperaiure conditions conducive to maintaining the fuel system at the desired temperature as fission occurs and heat is withdrawn from the reactor. A portion of the molten metal solution is withdrawn from the reactor vessel as fission continues, freed from metal fission products, and then returned to the reactor vessel. Removal of the metal fission products is accomplished by subjecting the molten metal solvent to nitrification under conditions of temperature and N/sub 2/ pressure to selectively precipitate in nitride form the fuel present. The precipitated nitride fuel is returned to the reactor, the metal fissionmore » products removed from the residual molten metal solution, and the remaining molten metal solution returned to the reactor vessel. Removal of the metal fission products from the residual molten metal solution may be effected by fractional distillation or by further nitrification under appropriate temperature and N/sub 2/ pressure conditions. (UK)« less" @default.
- W3141535823 created "2021-04-13" @default.
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- W3141535823 date "1973-07-18" @default.
- W3141535823 modified "2023-09-24" @default.
- W3141535823 title "Improvements in or relating to nuclear reactors" @default.
- W3141535823 hasPublicationYear "1973" @default.
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