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filingDate 1993-05-12-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_09ce00b38f13d9cffe42b57ac80edce3
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publicationDate 1994-11-25-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber JP-H06324189-A
titleOfInvention Molten salt electrorefining method
abstract (57) [Summary] [Objective] The electrolytic refining process rate in the dry reprocessing of spent metal fuels is improved, and the useful nuclear fuel components with high purity can be produced without accompanying incidental precipitation of fission products. It is intended to provide a molten salt electrolytic refining method that can be purified and recovered. [Composition] The molten metal phase 24 having a metal fuel component concentration of 0.01% by weight or more is used as a common bottom surface, and the molten salt phase 25 having a metal fuel component concentration of 0.1% by weight or more forming an electrolytic bath on the molten metal phase 24 is electrically insulating. Are partitioned concentrically by the annular partition wall 27 of the above, and the cathode 28 and the molten salt phase inside are partitioned into the partitioned molten salt phase 25b on the outside. The spent metal fuel holding means 29 which also serves as an anode is immersed in 25a, and the molten metal phase 24 is applied to the cathode 28 as an anode, The molten metal phase 24 is used as a cathode for the spent metal fuel 31, The present invention is characterized in that electricity is applied by one voltage application means 30 to simultaneously dissolve the anode of the spent nuclear fuel 31 and electrolytically deposit the refined metal fuel 34 on the surface of the cathode 28.
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