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U.S. Department of Energy
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Waste management analysis for the nuclear fuel cycle: parts I and II. Progress report for period ending March 31, 1977

Technical Report ·
DOI:https://doi.org/10.2172/7293410· OSTI ID:7293410
Preliminary evaluation of leaching, acid digestion, and fusion methods for actinide recovery from incinerator ash was begun. Cold ash from the fluidized bed incinerator was used as a stand-in for contaminated ash being prepared. Solubilization of ash was used as the measure of method efficiency. Fusion with basic fluxes appears to be most promising both with respect to actinide recovery efficiency and minimum impact on waste volume and form. Evaluation was begun of methods and recycle preparation problems for salt waste and waste water streams. A feasibility study for removing actinides from the salt wastes with a bidentate organophosphorous extractant was initiated. The composition of these waste streams was defined and actinide extraction coefficients, using dihexyl-N, N-diethylcarbamylmethylene phosphonate as the extractant, were determined as a function of nitric acid concentration. For the waste water streams, preliminary flow sheets were developed for purifying water by reverse osmosis.
Research Organization:
Atomics International Div., Golden, Colo. (USA)
DOE Contract Number:
EY-76-C-04-3533
OSTI ID:
7293410
Report Number(s):
RFP-2667
Country of Publication:
United States
Language:
English