Processing fissile material mixtures containing zirconium and/or carbon
Patent
·
OSTI ID:1086795
A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.
- Research Organization:
- DOENE (USDOE Office of Nuclear Energy, Science and Technology (NE) (United States))
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- FC01-07NE24502
- Assignee:
- U.S. Department of Energy (Washington, DC)
- Patent Number(s):
- 8,475,747
- Application Number:
- 12/484,561
- OSTI ID:
- 1086795
- Country of Publication:
- United States
- Language:
- English
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