FIELD: recycling nuclear power-generating materials.
SUBSTANCE: proposed method intended to enable reuse of uranium extracted from spent nuclear fuel in fuel cycle of light-water reactors by reducing its isotope involves increase of 235U isotope content in regenerated uranium to 2.0 - 7.0 mass percent at the same time reducing relative concentration of isotopes 232U, 234U, and 236U including direct enrichment of raw regenerated uranium hexafluoride in gas-centrifuge isotope-separating cascade; raw regenerated uranium is enriched by 235U isotope to content of 21.0 - 90.0 mass percent in double cascade during extraction of reduced fuel material with 235U isotope content not over 50.0%, preferably 2.0 - 36.0 mass percent, through waste flow of second ordinary cascade. Enrichment in first ordinary cascade is conducted up to 235U content of 3.5 - 10.0 mass percent or 21.0 - 35.0 mass percent. This method provides for attaining desired enrichment of regenerated uranium by 235U isotope at low content of noxious isotopes.
EFFECT: enhanced quality of regenerated uranium reduction due to absolute and relative control of noxious isotope content.
7 cl, 3 dwg, 5 tbl
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Authors
Dates
2004-12-20—Published
2002-12-17—Filed