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NUCLEAR COMBUSTIBLE PURIFYING PROCESS AND CENTRIFUGAL EXTRACTOR FOR THE SAME

机译:相同的核可燃净化过程和离心萃取器

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.
机译:通过将乏核燃料溶解在硝酸水溶液中并通过溶剂萃取分离并回收所得燃料溶液中所包含的核素,来对乏核燃料进行后处理。一种用于处理乏核燃料的方法,包括:价电解调节步骤(S4),其中将燃料溶液中包含的核素进行电解还原,而不会除去裂变产物(FP)或次要act系元素(MA),直到at的价变为0以燃料溶液中所含p的化合价为参数,溶剂萃取效率低的水平;核素分离步骤(S5),其中,使用提取燃料溶液中所含铀的提取溶剂,将经过步骤d价(S4)电解调节的燃料溶液中的铀分配给提取溶剂。

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