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filingDate 1999-04-14-04:00^^<http://www.w3.org/2001/XMLSchema#date>
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publicationDate 2000-10-24-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber JP-2000298190-A
titleOfInvention Reprocessing of spent nuclear fuel
abstract (57) Abstract: In a method for reprocessing nuclear fuel using a molten salt, the method includes a step of dissolving an oxide fuel by electrolysis at an anode, and a method for recovering uranium and plutonium recovered. Provided is a method for suppressing mixing of a noble metal. By using an inert gas as a cover gas on a molten salt, it is possible to control the oxygen partial pressure which affects the dissolution potential of a noble metal and uranium and plutonium. This has the effect of suppressing the incorporation of highly radioactive noble metals into uranium and / or plutonium and enabling low-cost operation of the fuel production process.
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