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
- Country of Publication:
- United States
- Language:
- English
Similar Records
URANIUM RECOVERY AND PURIFICATION PROCESS AND PRODUCTION OF HIGH PURITY URANIUM TETRAFLUORIDE
Purification of uranium by selective sorption of uranyl chloride on anion resin
Anion exchange separation of uranium, thorium and bismuth
Patent
·
Sun Dec 31 23:00:00 EST 1961
·
OSTI ID:4802596
Purification of uranium by selective sorption of uranyl chloride on anion resin
Technical Report
·
Wed Jan 31 23:00:00 EST 1973
·
OSTI ID:4937382
Anion exchange separation of uranium, thorium and bismuth
Journal Article
·
Fri Jun 01 00:00:00 EDT 1962
· Fresenius' Zeitschrift fuer Analytische Chemie
·
OSTI ID:4758324