RECOVERY OF URANIUM FROM TUNGSTEN
Abstract
A method is presented for the rccovery of uranium which has adhered to tungsten parts in electromagnetic isotope separation apparatus. Such a tungsten article is dissolved electrolytically in 20% NaOH by using the tungsten article as the anode. The resulting solution, containing soluble sodium lungstate and an insoluble slime, is then filtered. The slime residue is ignited successively with sodium nitrate and sodium pyrosulfate and leashed, and the resulting filtrates are combined with the original filtrate. Uranium is then recovered from the combined flltrates by diuranate precipitation.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4253423
- Patent Number(s):
- 2872394
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C25 - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES C25C - PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS
- NSA Number:
- NSA-13-013321
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ANODES; CHEMICAL REACTIONS; COMBUSTION; ELECTROLYSIS; FILTERS; ISOTOPE SEPARATION; MASS SPECTROMETERS; PRECIPITATION; QUANTITY RATIO; RECOVERY; SLURRIES; SODIUM COMPOUNDS; SODIUM HYDROXIDES; SODIUM NITRATES; SODIUM SULFATES; SOLUBILITY; TUNGSTEN; TUNGSTEN OXIDES; URANATES; URANIUM
Citation Formats
Newnam, K. RECOVERY OF URANIUM FROM TUNGSTEN. United States: N. p., 1959.
Web.
Newnam, K. RECOVERY OF URANIUM FROM TUNGSTEN. United States.
Newnam, K. Sun .
"RECOVERY OF URANIUM FROM TUNGSTEN". United States.
@article{osti_4253423,
title = {RECOVERY OF URANIUM FROM TUNGSTEN},
author = {Newnam, K},
abstractNote = {A method is presented for the rccovery of uranium which has adhered to tungsten parts in electromagnetic isotope separation apparatus. Such a tungsten article is dissolved electrolytically in 20% NaOH by using the tungsten article as the anode. The resulting solution, containing soluble sodium lungstate and an insoluble slime, is then filtered. The slime residue is ignited successively with sodium nitrate and sodium pyrosulfate and leashed, and the resulting filtrates are combined with the original filtrate. Uranium is then recovered from the combined flltrates by diuranate precipitation.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {2}
}
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