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Title: 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:
OSTI Identifier:
4209635
Patent Number(s):
2903402
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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}
}