Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel
According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-05ID14517
- Assignee:
- U.S. Department of Energy (Washington, DC)
- Patent Number(s):
- 10,418,138
- Application Number:
- 16/166,232
- OSTI ID:
- 1576313
- Resource Relation:
- Patent File Date: 2018 Oct 22
- Country of Publication:
- United States
- Language:
- English
Pyroelectrochemical process for reprocessing irradiated nuclear fuels
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patent | October 1981 |
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