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publicationDate 1997-05-20-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber RU-2079909-C1
titleOfInvention Method of nuclear fuel pyrochemical regeneration
abstract FIELD: irradiated and defective nuclear fuel processing, in particular processing of mononitride uranium-plutonium fuel. SUBSTANCE: container is loaded with nitride fuel and electrolyte is used, composition of which has at least 15 mass % of uranium trichloride. Electrolyte is heated up to temperature of no less than 600 C and electrical current with density of no more than 0.3 A/sq cm is created on container and of no more then 0.4 A/sq cm - on electrode. Besides, on low-melting electrode electrical current with density of no more than 0.1 A/sq sm is created and molten bath is heated up to temperature of no more than 700 C. Low-melting metal or alloy, that is more positive, than uranium nitride, is placed in container with nitride fuel. Then the metal or alloy is dissolved in container and uranium and plutonium are settled on low-melting electrode - cathode. EFFECT: improved process. 5 cl, 2 tbl
isCitedBy http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2022039631-A1
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http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2562809-C1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2766563-C2
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2603844-C1
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