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- W2296924256 abstract "The reprocessing of uranium fuel materials from zirconium-enriched reactor wastes by evaporation of UF/sub 6/ and its absorption in NaF are diacussed. The U-- Zr alloy is reacted with hydrofluoric acid and then fluorine gas. (M.C.G.)" @default.
- W2296924256 created "2016-06-24" @default.
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- W2296924256 date "1962-01-01" @default.
- W2296924256 modified "2023-09-26" @default.
- W2296924256 title "THE REPROCESSING OF URANIUM FUEL MATERIALS" @default.
- W2296924256 hasPublicationYear "1962" @default.
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