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Title: URANIUM RECOVERY AND PURIFICATION PROCESS AND PRODUCTION OF HIGH PURITY URANIUM TETRAFLUORIDE

Patent ·
OSTI ID:4312449

A process is described wherein an anionic exchange technique is employed to separate uramium from a large variety of impurities. Very efficient and economical purification of contamimated uranium can be achieved by treatment of the contaminated uranium to produce a solution containing a high concentration of chloride. Under these conditions the uranium exists as an aniomic chloride complex. Then the uranium chloride complex is adsorbed from the solution on an aniomic exchange resin, whereby a portion of the impurities remain in the solution and others are retained with the uramium by the resin. The adsorbed impurities are then removed by washing the resin with pure concentrated hydrochloric acid, after which operation the uranium is eluted with pure water yielding an acidic uranyl chloride solution of high purity.

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-12-004592
Assignee:
U.S. Atomic Energy Commission
Patent Number(s):
US 2806764
OSTI ID:
4312449
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-58
Country of Publication:
United States
Language:
English

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