Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
This report presents a review of publicly available documents providing validations of SCALE code system capabilities for depletion and shielding calculations. The validation studies primarily used information available in the Spent Fuel Isotopic Composition Database, the Shielding Integral Benchmark Archive and Database, and the International Criticality Safety Benchmark Evaluation Project Handbook. Validation results based on radiochemical assay data and shielding benchmark experiments relevant to spent nuclear fuel shielding applications are summarized in this report. The information summarized in this report supports pressurized water reactor and boiling water reactor spent fuel storage and transportation safety analyses.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1906576
- Report Number(s):
- ORNL/SPR-2022/2692
- Country of Publication:
- United States
- Language:
- English
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