CONCENTRATION OF Pu USING AN IODATE PRECIPITATE
A method is given for separating plutonium from lanthanum in a lanthanum fluoride carrier precipitation process for the recovery of plutonium values from an aqueous solution. The carrier precipitation process includes the steps of forming a lanthanum fluoride precipi- . tate, thereby carrying plutonium out of solution, metathesizing the fluoride precipitate to a hydroxide precipitate, and then dissolving the hydroxide precipitate in nitric acid. In accordance with the invention, the nitric acid solution, which contains plutonium and lanthanum, is made 0.05 to 0.15 molar in potassium iodate. thereby precipitating plutonium as plutonous iodate and the plutonous iodate is separated from the lanthanum- containing supernatant solution.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-015719
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2926067
- OSTI ID:
- 4184455
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
Similar Records
DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES
TRANSURANIC ELEMENT, COMPOSITION THEREOF, AND METHODS FOR PRODUCING SEPARATING AND PURIFYING SAME