FIELD: recovery of spent nuclear fuel.
SUBSTANCE: proposed method meant for raising content of 235U isotope in recovered uranium to 2.0 - 7.0 mass percent while reducing absolute or relative concentration of 232U, 234U, and 236U isotopes includes direct enrichment of raw uranium regenerate in isotope-separating gas-centrifuge cascade and dilution of regenerated uranium hexafluoride by natural uranium hexafluoride to mass not exceeding that of raw uranium regenerate. Raw uranium regenerate is enriched by 235U isotope to 21.0 - 35.0 mass percent.
EFFECT: enhanced quality of recovered uranium.
2 cl, 1 dwg, 6 tbl
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Authors
Dates
2004-09-10—Published
2002-11-04—Filed