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NUCLEAR COMBUSTIBLE PURIFYING PROCESS AND CENTRIFUGAL EXTRACTOR FOR THE SAME
NUCLEAR COMBUSTIBLE PURIFYING PROCESS AND CENTRIFUGAL EXTRACTOR FOR THE SAME
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机译:相同的核可燃净化过程和离心萃取器
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摘要
A spent nuclear fuel is reprocessed by dissolving spent nuclear fuel in an aqueous solution of nitric acid and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A process for reprocessing spent nuclear fuel comprises: a valence electrolytic adjustment step (S4) in which nuclides contained in the fuel solution are electrolytically reduced without removing fission products (FP) or minor actinides ( MA) until the valence of the plutonium is at a level at which the solvent extraction efficiency is low by using the valence of the plutonium contained in the fuel solution as a parameter; and a nuclide separation step (S5) in which, using an extraction solvent that extracts uranium contained in the fuel solution, uranium is dispensed from the fuel solution subjected to step d valence (S4) electrolytic adjustment to the extraction solvent.
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