URANIUM RECOVERY PROCESS
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4252948
- Patent Number(s):
- 2873165
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-13-013385
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; AGRICULTURE; CHEMICAL REACTIONS; ELECTRIC CHARGES; FERTILIZERS; LEACHING; PHOSPHATES; PRECIPITATION; RECOVERY; REDUCTION; SOLUTIONS; TRACE AMOUNTS; URANIUM; URANIUM FLUORIDES
Citation Formats
Bailes, R H, Long, R S, Olson, R S, and Kerlinger, H O. URANIUM RECOVERY PROCESS. United States: N. p., 1959.
Web.
Bailes, R H, Long, R S, Olson, R S, & Kerlinger, H O. URANIUM RECOVERY PROCESS. United States.
Bailes, R H, Long, R S, Olson, R S, and Kerlinger, H O. Tue .
"URANIUM RECOVERY PROCESS". United States.
@article{osti_4252948,
title = {URANIUM RECOVERY PROCESS},
author = {Bailes, R H and Long, R S and Olson, R S and Kerlinger, H O},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {2}
}
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