Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks
The U.S. Nuclear Regulatory Commission (NRC) is currently reviewing the technical specifications for spent fuel storage casks in an effort to develop standard technical specifications (STS) that define the allowable spent nuclear fuel (SNF) contents. One of the objectives of the review is to minimize the level of detail in the STS that define the acceptable fuel types. To support this initiative, this study has been performed to identify potential fuel specification parameters needed for criticality safety and radiation shielding analysis and rank their importance relative to a potential compromise of the margin of safety.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission (US)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 814530
- Report Number(s):
- ORNL/TM-2000/385; TRN: US0304259
- Resource Relation:
- Other Information: PBD: 8 Mar 2001
- Country of Publication:
- United States
- Language:
- English
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