ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES
Abstract
An electrochemical process is described for separating uranium from fission products. The method comprises subjecting the mass of uranium to anodic dissolution in an electrolytic cell containing aqueous alkali bicarbonate solution as its electrolyte, thereby promoting a settling from the solution of a solid sludge from about the electrodes and separating the resulting electrolyte solution containing the anodically dissolved uranium from the sludge which contains the rare earth fission products.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4318761
- Patent Number(s):
- 2834722
- 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-12-014404
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
- Subject:
- PATENTS; ALKALI METALS; ANIONS; CARBONATES; DECONTAMINATION; ELECTROCHEMISTRY; ELECTRODES; ELECTROLYTIC CELLS; FISSION PRODUCTS; PATENT; RARE EARTHS; RECOVERY; RODS; SOLUTIONS; URANIUM COMPOUNDS
Citation Formats
McLaren, J A, and Goode, J H. ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES. United States: N. p., 1958.
Web.
McLaren, J A, & Goode, J H. ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES. United States.
McLaren, J A, and Goode, J H. Tue .
"ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES". United States.
@article{osti_4318761,
title = {ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES},
author = {McLaren, J A and Goode, J H},
abstractNote = {An electrochemical process is described for separating uranium from fission products. The method comprises subjecting the mass of uranium to anodic dissolution in an electrolytic cell containing aqueous alkali bicarbonate solution as its electrolyte, thereby promoting a settling from the solution of a solid sludge from about the electrodes and separating the resulting electrolyte solution containing the anodically dissolved uranium from the sludge which contains the rare earth fission products.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {5}
}
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