IMPROVEMENTS IN OR RELATING TO THE RECOVERY OF URANIUM
Patent
·
OSTI ID:4081015
Magnesium fluoride and calcium fluoride slags resulting from uranium production from UF/sub 4/ may be leached for uranium recovery in stainless steel vessels with nitric acid solutions of such concentrations that the final acidity is 0.5 to 5N; if the temperature is restricted to 40 to 80 deg C, the corrosion rate of the vessel is low and acceptable. The resulting aqueous solution may be treated with TBP in the usual manner to remove uranium. Separan 2610 may be used as a conditioning or flocculating agent to settle the fine particles before filtering the leach slurry. One example of this method is given. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-006069
- OSTI ID:
- 4081015
- Report Number(s):
- GB 853343
- Country of Publication:
- United Kingdom
- Language:
- English
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