Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Waste management analysis for the nuclear fuel cycle. I. Actinide recovery from aqueous salt wastes

Technical Report ·
DOI:https://doi.org/10.2172/6221971· OSTI ID:6221971
A preliminary feasibility study of solvent extraction methods has been completed for removing actinides from selected salt wastes likely to be produced during reactor fuel fabrication and reprocessing. The use of a two-step solvent extraction system, tributyl phosphate (TBP) followed by a bidentate organophosphorus extractant (DHDECMP), appears most efficient for removing actinides from salt waste. The TBP step would remove most of the plutonium and >99.99% of the uranium. The second step, using DHDECMP, would remove >99.91% of the americium, the remaining plutonium (>99.98%), and other actinides from the acidified salt waste.
Research Organization:
Atomics International Div., Golden, CO (USA). Rocky Flats Plant
DOE Contract Number:
EY-76-C-04-3533
OSTI ID:
6221971
Report Number(s):
RFP-2812
Country of Publication:
United States
Language:
English