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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, April 1--September 30, 1977. [Actinide recovery from waste]

Technical Report ·
DOI:https://doi.org/10.2172/6441796· OSTI ID:6441796
A preliminary evaluation of methods for the salt waste and waste water streams and recycle preparation problems was completed. A feasibility study for removing actinides from synthetic salt waste showed that a bidentate organophosphorus extractant is the most efficient for actinide removal. The evaluation of adsorbents for removing detergents and anions from waste water suggests the use of a combination of non-ionic and a strong base ion exchange resin for best results. Evaluation of leaching and dissolution methods for the recovery of actinides from combustible waste (incinerator ash) was continued. Two promising recovery methods are: (1) reaction with cerium(IV) in nitric acid to solubilize carbon and actinide oxides, and (2) fusion with carbonate--nitrate mixtures. Silica proved to be a problem. If dissolved, it interferes with subsequent actinide recovery by forming polysilicic acid upon acidification. If not solubilized, silica-encapsulated actinide oxides may not be contacted by the dissolvent. Pretreatment of ash by refluxing with greater than or equal to 6M sodium hydroxide appears to remove silica, simplifying subsequent recovery steps.
Research Organization:
Atomics International Div., Golden, CO (USA). Rocky Flats Plant
Sponsoring Organization:
USDOE
DOE Contract Number:
EY-76-C-04-3533
OSTI ID:
6441796
Report Number(s):
RFP-2749
Country of Publication:
United States
Language:
English