Method for cleaning solution used in nuclear fuel reprocessing
AssigneeThe United States of America as represented by the United States Department of Energy
InventorsOthar K. Tallent, David J. Crouse, James C. Mailen
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Abstract
Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.
Claims2
A method for removing a complex of uranium, plutonium, or zirconium with mono-butyl phosphate or di-n-butyl phosphate degradation product of tri-n-butyl phosphate in a nuclear fuel reprocessing solution containing said complex, tri-n-butyl phosphate and a hydrocarbon diluent, comprising contacting said solution with an aqueous solution of a salt selected from the group consisting of hydrazine oxalate, hydrazine tartrate, hydrazine lactate and hydrazine glycolate, to thereby obtain (1) an organic phase which contains said tri-n-butyl phosphate and said hydrocarbon diluent and is substantially free of said complex and (2) a spent aqueous phase containing the uranium, plutonium, or zirconium of said complex with the degradation product.
Dependencies are inferred from the claim text.