MIXTURE EXTRACTANT RECOVERING ACTINIDE ELEMENT IN ACIDIC SOLUTION

PROBLEM TO BE SOLVED: To provide a mixture extractant capable of extracting an actinide element such as U, Pu and a transplutonium element from a radioactive liquid waste in reprocessing a spent nuclear fuel. SOLUTION: The mixture extractant is composed of a solution containing dihexyl-N, N-diethylcarbamoylphosphonate, an organophosphorous extractant with a bidentate coordination, in a polar diluent, using bis-tetrafluoropropyl ether of diethylene glycol as the polar diluent, wherein in a ratio of each component, the extratant with the bidentate coordination is 0.1-1.2 M/L and the diluent is balanced. And alternatively, the mixture extractant is composed of the solution containing octylphenyl-N, N-diisobutylcarbamoylphosphine oxide, the organophosphorous extractant with the bidentate coordination, in the polar diluent, using a mixture of m-nitrobenzotrifluoride(MNBTF) and TBP as the polar diluent, wherein in the ratio of each component, the extractant with the bidentate coordination is 0.1-1.2 M/L, TBP is 0.3-1.1 M/L and MNBTF is balanced. COPYRIGHT: (C)2006,JPO&NCIPI