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Title: 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}
}