Recovery of transplutonium elements from nuclear reactor waste

Details Recovery of transplutonium elements from nuclear reactor waste Recovery of transplutonium elements from nuclear reactor waste

C - Chemistry, Metallurgy

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B

53/162, 53/190

C22B 60/00 (2006.01) C01F 17/00 (2006.01) C01G 56/00 (2006.01) C22B 59/00 (2006.01) C22B 60/02 (2006.01) C22B 60/04 (2006.01) G21F 9/00 (2006.01)

Patent

CA 1081969

ABSTRACT OF THE DISCLOSURE A method of separating actinide values from nitric acid waste solutions resulting from reprocessing of irradiated nuclear fuels comprises oxalate precipitation of the major portion of actinide and lanthanide values to provide a trivalent fraction suitable for sub- sequent actinide/lanthanide partition, exchange of actinide and lanthanide values in the supernate onto a suitable cation exchange resin to provide an intermediate-lived raffinate waste stream sub- stantially free of actinides, and elution of the actinide values from the exchange resin. The eluate is then used to dissolve the trivalent oxalate fraction prior to actinide/lanthanide partition or may be combined with the reprocessing waste stream and recycled.

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