RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES
Abstract
An electrolytic process for recovering uranium from a graphite fuel element is described. The uraniumcontaining graphite body is disposed as the anode of a cell containing a nitric acid electrolyte and a 5 amp/cm/sup 2/ current passed to induce a progressive disintegration of the graphite body. The dissolved uranium is quickly and easily separated from the resulting graphite particles by simple mechanical means, such as centrifugation, filtration, and decontamination.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4209635
- Patent Number(s):
- 2903402
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C25 - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES C25B - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES FOR THE PRODUCTION OF COMPOUNDS OR NON-METALS
C - CHEMISTRY C25 - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES C25C - PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS
- NSA Number:
- NSA-14-006374
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ANODES; CENTRIFUGATION; DECOMPOSITION; DECONTAMINATION; ELECTROLYSIS; ELECTROLYTES; ELECTROLYTIC CELLS; FILTERS; FUEL ELEMENTS; GRAPHITE; NITRIC ACID; RECOVERY; URANIUM
Citation Formats
Fromm, Jr, L W. RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES. United States: N. p., 1959.
Web.
Fromm, Jr, L W. RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES. United States.
Fromm, Jr, L W. Tue .
"RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES". United States.
@article{osti_4209635,
title = {RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES},
author = {Fromm, Jr, L W},
abstractNote = {An electrolytic process for recovering uranium from a graphite fuel element is described. The uraniumcontaining graphite body is disposed as the anode of a cell containing a nitric acid electrolyte and a 5 amp/cm/sup 2/ current passed to induce a progressive disintegration of the graphite body. The dissolved uranium is quickly and easily separated from the resulting graphite particles by simple mechanical means, such as centrifugation, filtration, and decontamination.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {9}
}