发明名称 METHOD OF REPROCESSING SPENT NUCLEAR FUEL AND CENTRIFUGAL EXTRACTOR
摘要 <P>PROBLEM TO BE SOLVED: To provide a method of reprocessing spent nuclear fuel which enables the recovery of high-purity uranium without setting up the step of separating plutonium solely from the spent nuclear fuel and also makes it difficult to recover the reprocessed plutonium isolatedly, which brings about excellent deterrent effects on nuclear proliferation. <P>SOLUTION: In the method of reprocessing the spent nuclear fuel by dissolving it in a nitric acid water solution to separate and recover nuclides contained in the obtained fuel dissolved liquid through solvent extraction, the electrolysis valency adjustment step of making electrolytic reduction on dissolved nuclides contained in the fuel dissolved liquid with the valency of Pu contained in the fuel dissolved liquid used as the reference both till the valency of the plutonium becomes trivalent and without removing fission products (FP) or minor actinide (MA), and the nuclide separation step of using a tributyl phosphate (TBP) solvent to distribute Pu from the fuel dissolved liquid having undergone the electrolysis valency adjustment process into the TBP solvent are set up. <P>COPYRIGHT: (C)2010,JPO&INPIT
申请公布号 JP2010043953(A) 申请公布日期 2010.02.25
申请号 JP20080208194 申请日期 2008.08.12
申请人 TOSHIBA CORP 发明人 FUJITA REIKO;FUSE YUKIMOTO;MIZUGUCHI KOJI;NAKAMURA HITOSHI;UTSUNOMIYA KAZUHIRO;TANAKA NOBUHIKO
分类号 G21C19/46 主分类号 G21C19/46
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