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Kwon, S.W.; Park, K.M.; Kim, J.G.; Kim, I.T.; Park, S.B.
Actinide and Fission Product Partitioning and Transmutation2015
Actinide and Fission Product Partitioning and Transmutation2015
AbstractAbstract
[en] Full text of publication follows: pyro-processing has been developed for the recovery of actinide elements from spent fuel due to its advantages of compactness, proliferation resistance, and reduction of a secondary waste generation. The solid cathode processing is necessary to separate the salt from the cathode, for the preparation of the uranium ingot with a high purity. An increase of the throughput of the salt removal process from uranium deposits, generated on the solid cathode of the electro-refiner in the pyro-process is necessary. In this study, an attempt to enlarge a throughput of the salt distiller with multilayer porous crucibles for the separation of the adhered salt in the uranium deposits generated from the electro-refiner was carried out. The feasibility of the porous crucibles was tested by the salt separation experiments. A two-step weight reduction was observed in the porous crucible. However, the salt weight only decreased at high temperature by distillation in a non-porous crucible. The first weight reduction was caused by the liquid salt penetration through the perforated crucible during the temperature elevation until the distillation temperature. The salt weight reduction started at about 450 deg. C. After the liquid salt flew out through the perforated crucible by gravity, the weight was kept constant up to the salt evaporation temperature. The second weight reduction started at about 650 deg. C. Besides the porous crucible, the concept of multiple crucibles (multilayer) was also proposed. Multilayer crucibles have a benefit to expand the evaporation surface area. It could be concluded that the multilayer porous crucible system is an effective way for the achievement of a high throughput performance in the salt separation process because the liquid salt of the uranium deposits can be separated during temperature elevation for the distillation and high surface area for salt evaporation. (authors)
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Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Nuclear Science Committee - NSC, 46, quai Alphonse Le Gallo, 92100 Boulogne Billancourt (France); 417 p; Jun 2015; p. 161; 13. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation; Seoul (Korea, Republic of); 23-26 Sep 2014; 2 refs.
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