FIELD: recovery of spent nuclear fuel.
SUBSTANCE: proposed method involves enhancement of uranium-235 isotope content in recovered uranium to 2.0-5.0 mass percent while reducing absolute and/or relative concentration of uranium even isotopes. Method includes division of isotope mixture of raw uranium reagent in gas-centrifuge isotope-division cascade and mixing of separated commercial isotope mixture with uranium thinner. Isotope mixture division is effected in two-cascade arrangement. Raw uranium reagent is enriched with uranium-235 fissionable isotope in first single cascade up to content over 90 mass percent. Second single cascade is used for cleaning isotope mixture from uranium-232 and uranium-234 isotopes. Select flow of second cascade enriched with uranium-235 isotope is conveyed as commercial isotope mixture for mixing up with uranium-thinner.
EFFECT: enhanced quality of reducing recovered uranium and minimized uranium-thinner requirement.
12 cl, 1 dwg, 6 tbl
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Authors
Dates
2006-08-27—Published
2004-04-13—Filed