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SEPARATION OF URANIUM, PLUTONIUM AND FISSION PRODUCTS

Patent ·
OSTI ID:4067415

A solvent extraction method for the treatment of neutron irradiated uranium in order to remove plutonium and uranium from the fission products and to separate the plutonium from the uradium is described. The irradiated uranium is dissolved in 2 to 4 N, preferable 3 N, nitric acid to provide an aqueous acidic solution of nitrate salts of uranium, plutonium, and fission products. The solution is then treated with dibutyl carbitol to extract the uranium and plutorium into the organic solvent phase. The organic solvent, dibutyl carbitol, is 1.8 N in nitric acid to avoid transfer of acid fr m the aqueous to the organic phase. The plutonium is separated from the uranium in the organic phase by extraction into an aqueous nitrate salt solution containing a reducing agent for the plutomum. The aqueous phase containing the plutonium is separated from the solvent phase. The fission pr ducts are extracted as nitrates in the aqueous phase. (N.W.R.)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-15-020804
OSTI ID:
4067415
Report Number(s):
CA 613891
Country of Publication:
Canada
Language:
English

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