WET FLUORIDE SEPARATION METHOD
Patent
·
OSTI ID:4296252
The separation of U/sup 233/ from thorium, protactinium, and fission products present in neutron-irradiated thorium is accomplished by dissolving the irradiated materials in aqueous nitric acid, adding either a soluble fluoride, iodate, phosphate, or oxalate to precipltate the thorium, separating the precipltate from the solution, and then precipitating uranlum and protactinium by alkalizing the solution. The uranium and protactinium precipitate is removcd from the solution and dissolved in nitric acid. The uranyl nitrate may then be extracted from the acid solution by means of ether, and the protactinium recovered from the aqueous phase.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-13-008412
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2861866
- OSTI ID:
- 4296252
- Country of Publication:
- United States
- Language:
- English
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