Process for reprocessing spent nuclear fuels by utilizing...

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

Reexamination Certificate

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C423S250000, C423S251000, C423S253000

Reexamination Certificate

active

07011798

ABSTRACT:
A reprocessing process of spent nuclear fuels for roughly separating U and U—Pu from FP, TRU and the like in a nitric acid solution of spent nuclear fuels by utilizing phenomenon of cocrystallization of hexavalent U and Pu. For example, spent nuclear fuels are sheared and dissolved in nitric acid, and insoluble residues in the nitric acid solution are removed. Then, a nitric acid concentration in the solution is adjusted and a valence of Pu in the solution is adjusted to tetravalence. The solution is then cooled to crystallize uranyl nitrate hydrate crystals and separated into the crystals and a mother liquor, and the separated crystals are recovered as a U product. Then, a nitric acid concentration in the separated mother liquor is adjusted and a valance of U and Pu in the mother liquor is adjusted to hexavalence, and the mother liquor is cooled to crystallize uranyl-plutonyl nitrate hydrate crystals which are separated and recovered as a U—Pu mixed product.

REFERENCES:
patent: 4759878 (1988-07-01), Henrich et al.
patent: 5112581 (1992-05-01), Ohuchi et al.
patent: 6033636 (2000-03-01), Todokoro et al.
patent: 863571 (1961-03-01), None

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