TREATMENT OF NUCLEAR FUELS
Patent
·
OSTI ID:4837763
Irradiated fuel, such as uranium oxides or U- Al alloys, are dissolved in KAlCl/sub 4/ at 400 to 100 deg C. Formation of Al/sub 2/O/sub 3/ can be prevented by passing CCl/sub 4/ through the molten mass. Aluminum is added, the mass is cooled to 400 to 500 deg C and the two phases are separated. The metallic phase consists of an Al-U alloy while the salt phase contains the plutonium and the greater part of the fission products. (NPO)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-032254
- OSTI ID:
- 4837763
- Report Number(s):
- FR 1229237
- Country of Publication:
- France
- Language:
- English
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