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filingDate 1993-06-07-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_bd9eb8bca5a3188d7c024c428328f230
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publicationDate 1994-12-22-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber JP-H06347589-A
titleOfInvention Oxidative extraction method of nebutunium in nuclear fuel reprocessing co-decontamination process
abstract (57) [Summary] [Purpose] In the co-decontamination process of the nuclear fuel reprocessing process, 5 In the method of oxidizing hexavalent nebutunium (Np) to hexavalent, an electrolysis method that is excellent in remote operation and does not generate secondary waste is used. [Structure] In the co-decontamination step of the nuclear fuel reprocessing step, a method of oxidizing pentavalent Np, which is not extracted in an organic solvent, to hexavalent and extracting it into an organic solvent together with hexavalent U and Pu, In the process, U, Pu and hexavalent Np Is extracted with an organic solvent, and almost pentavalent N is present in the solution. In the extraction stage where only p and fission products are present, the valence of Np is electrolytically oxidized from pentavalent to hexavalent.
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