SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS
Patent
·
OSTI ID:4727599
A process is described for separating uranium from a nuclear fuel element comprising a uranium-containing core and a ferritic stainless steel clad by heating said element in a non-carburizing atmosphere at a temperature in the range 850-1050 un. Concent 85% C, rapidly cooling the heated element through the temperature range 815 un. Concent 85% to 650 EC to avoid annealing said steel, and then contacting the cooled element with an aqueous solution of nitric acid to selectively dissolve the uranium. (AEC)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-17-021805
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 3089751
- OSTI ID:
- 4727599
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
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Chemical interaction of metallic fuel with austenitic and ferritic stainless steel cladding
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