A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications
Spent nuclear fuel (SNF) cask systems are typically designed for storage and transportation of a variety of fuel assembly and non-fuel hardware (NFH) types (e.g., control rod and burnable absorber rod assemblies) with a wide range of irradiation and decay characteristics. This report analyzes the dependencies of SNF radiation source terms, activated cobalt in hardware materials, and external cask dose rate, with a focus on fuel depletion parameters. This study employed several modeling approaches to help identify the bounding input parameters for shielding analyses. The calculations presented in this report were performed with the analysis sequences within the SCALE code system, which include ORIGEN, ORIGAMI, OPUS, POLARIS, and TRITON for depletion/decay calculations, and MAVRIC for dose rate calculations. MAVRIC uses the Monte Carlo method to solve particle transport problems involved in shielding calculations. Generic cask designs were used in the various MAVRIC calculations.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1867782
- Report Number(s):
- ORNL/SPR-2021/2373; TRN: US2308379
- Country of Publication:
- United States
- Language:
- English
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