URANIUM RECOVERY PROCESS
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4207656
- Patent Number(s):
- 2897048
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02P - CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- NSA Number:
- NSA-14-002502
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; COMPLEXES; FILTERS; LEACHING; MAGNESIUM FLUORIDES; METALS; PRESSURE; PRODUCTION; RECOVERY; REDUCTION; SLAGS; SODIUM CARBONATES; SOLUTIONS; TEMPERATURE; URANIUM; WATER
Citation Formats
Stevenson, J W, and Werkema, R G. URANIUM RECOVERY PROCESS. United States: N. p., 1959.
Web.
Stevenson, J W, & Werkema, R G. URANIUM RECOVERY PROCESS. United States.
Stevenson, J W, and Werkema, R G. Tue .
"URANIUM RECOVERY PROCESS". United States.
@article{osti_4207656,
title = {URANIUM RECOVERY PROCESS},
author = {Stevenson, J W and Werkema, R G},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {7}
}
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