URANIUM RECOVERY PROCESS
A method is described for recovering uranium values from uranium bearing phosphate solutions such as are encountered in the manufacture of phosphate fertilizers. The solution is first treated with a reducing agent to obtain all the uranium in the tetravalent state. Following this reduction, the solution is treated to co-precipitate the rcduced uranium as a fluoride, together with other insoluble fluorides, thereby accomplishing a substantially complete recovery of even trace amounts of uranium from the phosphate solution. This precipitate usually takes the form of a complex fluoride precipitate, and after appropriate pre-treatment, the uranium fluorides are leached from this precipitate and rccovered from the leach solution.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-13-013385
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2873165
- OSTI ID:
- 4252948
- Country of Publication:
- United States
- Language:
- English
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EXTRACTION OR RECOVERY OF URANIUM AND OTHER METALS