RECOVERY OF VALUABLE MATERIAL FROM GRAPHITE BODIES
Patent
·
OSTI ID:4209635
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.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-006374
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2903402
- OSTI ID:
- 4209635
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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