URANIUM LEACHING AND RECOVERY PROCESS
Patent
·
OSTI ID:4204182
A process is described for recovering uranium from carbonate leach solutions by precipitating uranium as a mixed oxidation state compound. Uranium is recovered by adding a quadrivalent uranium carbon;te solution to the carbonate solution, adjusting the pH to 13 or greater, and precipitating the uranium as a filterable mixed oxidation state compound. In the event vanadium occurs with the uranium, the vanadium is unaffected by the uranium precipitation step and remains in the carbonate solution. The uranium-free solution is electrolyzed in the cathode compartment of a mercury cathode diaphragm cell to reduce and precipitate the vanadium.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-006358
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2900229
- OSTI ID:
- 4204182
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:4204182
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OSTI ID:4204182
PROGRESS REPORT FOR THE PERIOD JULY 1, 1952 TO AUGUST 29, 1952
Technical Report
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Mon Dec 15 00:00:00 EST 1952
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OSTI ID:4204182