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Title: 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 DTIE; NSA-13-013385
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}
}