URANIUM RECOVERY PROCESS
The recovery of uranium from the acidic aqueous metal waste solutions resulting from the bismuth phosphate carrier precipitation of plutonium from solutions of neutron irradiated uranium is described. The waste solutions consist of phosphoric acid, sulfuric acid, and uranium as a uranyl salt, together with salts of the fission products normally associated with neutron irradiated uranium. Generally, the process of the invention involves the partial neutralization of the waste solution with sodium hydroxide, followed by conversion of the solution to a pH 11 by mixing therewith sufficient sodium carbonate. The resultant carbonate-complexed waste is contacted with a titanated silica gel and the adsorbent separated from the aqueous medium. The aqueous solution is then mixed with sufficient acetic acid to bring the pH of the aqueous medium to between 4 and 5, whereby sodium uranyl acetate is precipitated. The precipitate is dissolved in nitric acid and the resulting solution preferably provided with salting out agents. Uranyl nitrate is recovered from the solution by extraction with an ether such as diethyl ether.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-002481
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2893824
- OSTI ID:
- 4207775
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACETIC ACID
ACIDITY
ACIDS
ADSORPTION
BISMUTH PHOSPHATES
CHEMISTRY
COLLOIDS
ETHERS
FISSION PRODUCTS
IRRADIATION
MIXING
NEUTRONS
PHOSPHORIC ACID
PLUTONIUM
PRECIPITATION
RECOVERY
SALTING-OUT AGENTS
SILICON OXIDES
SODIUM CARBONATES
SODIUM COMPOUNDS
SODIUM HYDROXIDES
SOLVENT EXTRACTION
SULFURIC ACID
TITANATES
URANIUM
URANYL COMPOUNDS
URANYL NITRATES
WASTE SOLUTIONS
WATER