Recovery of transplutonium elements from nuclear reactor waste

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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423 11, 2523011R, C01G 5600

Patent

active

040256022

ABSTRACT:
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 subsequent 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 substantially 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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patent: 3781404 (1973-12-01), Conner et al.
patent: 3922231 (1975-11-01), Carlin et al.
Nuclear Science Abstracts, 23, 15956, Nozaki, et al.
Nuclear Science Abstracts, 21, 19742, Krawezyk-Obojska.

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