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U.S. Department of Energy
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URANIUM RECOVERY PROCESS

Patent ·
OSTI ID:4207656

The recovery of uranium from magnesium fluoride slag obtained as a by- product in the production of uranium metal by the bomb reduction prccess is presented. Generally the recovery is accomplished by finely grinding the slag, roasting ihe ground slag air, and leaching the roasted slag with a hot, aqueous solution containing an excess of the sodium bicarbonate stoichiometrically required to form soluble uranium carbonate complex. The roasting is preferably carried out at between 425 and 485 deg C for about three hours. The leaching is preferably done at 70 to 90 deg C and under pressure. After leaching and filtration the uranium may be recovered from the clear leach liquor by any desired method.

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-14-002502
Assignee:
U.S. Atomic Energy Commission
Patent Number(s):
US 2897048
OSTI ID:
4207656
Country of Publication:
United States
Language:
English

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