Storage of assemblies containing mixed-oxide fuel
Both fresh and spent mixed-oxide (MOX) assemblies exhibit physical characteristics that will necessitate additional measurements and analyses beyond those that are done for low-enriched uranium (LEU) assemblies. While none of these analyses or measurements require technological development, estimates for disposition costs and schedules must account for these factors. This report identifies those nuclear engineering analyses that will be required to demonstrate acceptability of MOX fuel assembly storage.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 582213
- Report Number(s):
- ORNL/TM-13424; ON: DE98052494; TRN: 98:009339
- Resource Relation:
- Other Information: PBD: Apr 1997
- Country of Publication:
- United States
- Language:
- English
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