Loading patent…
AssigneeJapan Nuclear Cycle Development Institute
InventorsMasaki Ozawa, Vasily Babain, Yury Fedorov, Andey Shadrin, Valery Romanovsky, Igor Smirnov, Boris Zilberman
Estimating the term…
Extraction mixture capable of recovering actinide elements such as U, Pu and transplutonium elements from radioactive liquid waste in reprocessing of spent nuclear fuel. One embodiment of the extraction mixture includes a solution of bidentate organophosphorus extractant, dihexyl-N,N-diethylcarbamoyl phosphonate in a polar diluent, wherein bis-tetrafluoropropyl ether of diethylene glycol is used as the polar diluent at the following ratio of components: 0.1-1.2 M/L of bidentate extractant and the rest of diluent. Another embodiment of the extraction mixture includes a solution of bidentate organophosphorus extractant, phenyloctyl-N,N-diisobutylcarbamoylphosphine oxide in a polar diluent, wherein a mixture of metanitrobenzotrifluoride with trialkylphosphate is used as the polar diluent at the following ratio of components: 0.1-1.2 M/L of bidentate extractant, 0.3-1.1 M/L of TBP, and the rest of MNBTF.
An extraction mixture for recovery of actinide elements from acidic solutions including a solution of bidentate organophosphorus extractant, dihexyl-N,N-diethylcarbamoyl phosphonate in a polar diluent, wherein bis-tetrafluoropropyl ether of diethylene glycol is used as the polar diluent at the following ratio of components:
An extraction mixture for recovery of actinide elements from acidic solutions including a solution of bidentate organophosphorus extractant, phenyloctyl-N,N-diisobutylcarbamoylphosphine oxide in a polar diluent, wherein a mixture of metanitrobenzotrifluoride with trialkylphosphate is used as the polar diluent at the following ratio of components:
Dependencies are inferred from the claim text.