Extraction mixture for recovery of actinide elements from...

Compositions – Absorptive – or bindive – and chemically yieldive

Reexamination Certificate

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C252S364000, C423S009000, C423S010000, C423SDIG014

Reexamination Certificate

active

07491345

ABSTRACT:
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.

REFERENCES:
patent: 6258333 (2001-07-01), Romanovskiy et al.
patent: 6468445 (2002-10-01), Romanovskiy et al.
patent: 01143837 (1989-06-01), None
patent: 1603552 (1994-07-01), None
S.M. Stoller et al., Reactor Handbook, Second Edition, vol. II, Fuel Reprocessing, 1961. pp. 101-102.
B.F. Myasoedov et al., “Method for extraction recovery of rare-earth and actinide elements,” Russian Certificate of Authorship No. 1524519, Aug. 23, 1992 (converted to Patent on Apr. 27, 1997).
E.P. Horwitz et al. “The Truex Process—A Process for the Extraction of the Transuranic Elements From Nitric Acid Wastes Utilizing Modified Purex Solvent,” Solvent Extraction and Ion Exchange, vol. 3 (1&2), 1985. pp. 75-109.

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