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U.S. Department of Energy
Office of Scientific and Technical Information

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