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publicationDate 2000-12-05-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber US-6156183-A
titleOfInvention Method of processing spent reactor fuel with magnesium alloy cladding
abstract A spent reactor fuel processing method is provided for recovering at least any one of metallic nuclear fuel materials, in which the reactor fuel is composed by covering the metallic nuclear fuel material with a cladding tube made of alloy and having a melting point lower than that of the metallic nuclear fuel material and end plugs made of alloy are mounted to both ends thereof. The processing method comprises a cladding tube smelting separation process, a molten salt electrorefining process and a salt evaporation separation process for recovering metallic uranium, uranium and plutonium, or uranium, plutonium and transuranium elements.
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