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Title: 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 DTIE; NSA-14-002502
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}
}