URANIUM RECOVERY PROCESS
Abstract
A process of recovering uranium from very low-grade ore residues is described. These low-grade uraniumcontaining hydroxide precipitates, which also contain hydrated silica and iron and aluminum hydroxides, are subjected to multiple leachings with aqueous solutions of sodium carbonate at a pH of at least 9. This leaching serves to selectively extract the uranium from the precipitate, but to leave the greater part of the silica, iron, and aluminum with the residue. The uranium is then separated from the leach liquor by the addition of an acid in sufficient amount to destroy the carbonate followed by the addition of ammonia to precipitate uranium as ammonium diuranate.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4330487
- Patent Number(s):
- 2830871
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-12-014392
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
- Subject:
- PATENTS; ACIDS; ALUMINUM HYDROXIDES; AMMONIA; AMMONIUM COMPOUNDS; DECOMPOSITION; HYDROXIDES; IRON HYDROXIDES; LEACHING; PATENT; PRECIPITATION; RECOVERY; RESIDUES; SEPARATION PROCESSES; SILICON OXIDES; SODIUM CARBONATES; SOLUTIONS; URANATES; URANIUM; WATER
Citation Formats
Kaufman, D. URANIUM RECOVERY PROCESS. United States: N. p., 1958.
Web.
Kaufman, D. URANIUM RECOVERY PROCESS. United States.
Kaufman, D. Tue .
"URANIUM RECOVERY PROCESS". United States.
@article{osti_4330487,
title = {URANIUM RECOVERY PROCESS},
author = {Kaufman, D},
abstractNote = {A process of recovering uranium from very low-grade ore residues is described. These low-grade uraniumcontaining hydroxide precipitates, which also contain hydrated silica and iron and aluminum hydroxides, are subjected to multiple leachings with aqueous solutions of sodium carbonate at a pH of at least 9. This leaching serves to selectively extract the uranium from the precipitate, but to leave the greater part of the silica, iron, and aluminum with the residue. The uranium is then separated from the leach liquor by the addition of an acid in sufficient amount to destroy the carbonate followed by the addition of ammonia to precipitate uranium as ammonium diuranate.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {4}
}
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