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Decontamination of alkaline radioactive waste by ion exchange

Journal Article · · Ind. Eng. Chem. Process Des. Dev.; (United States)
DOI:https://doi.org/10.1021/i260065a012· OSTI ID:6311328

An ion-exchange process was developed to remove cesium-137, strontium-90, and plutonium from alkaline salt solutions. About 20 million gal of alkaline salt cake and supernatant solution from processing nuclear fuels and materials for defense programs are presently stored at the Savannah River Plant. Ion exchange may be used to decontaminate this radioactive waste during a proposed waste solidification program. In development tests 100-L quantities of liquid waste were decontaminated. Decontamination factors were 4 x 10/sup 5/ for /sup 137/Cs, 5 x 10/sup 3/ for /sup 90/Sr, and 300 for Pu. The separated radionuclides were concentrated by a factor of 1500 and immobilized by adsorption onto zeolite. Residual /sup 137/Cs, /sup 90/Sr, and Pu activity in the decontaminated product was about 6 nCi/g. /sup 106/Ru, the most hazardous radionuclide remaining after /sup 137/Cs removal, will decay to 6 nCi/g about 10 years after the waste is processed.

Research Organization:
Savannah River Lab., Aiken, SC
OSTI ID:
6311328
Journal Information:
Ind. Eng. Chem. Process Des. Dev.; (United States), Journal Name: Ind. Eng. Chem. Process Des. Dev.; (United States) Vol. 17:1; ISSN IEPDA
Country of Publication:
United States
Language:
English