The US Nuclear Regulatory Commission (NRC) is responsible for licensing spent fuel storage casks under Title 10 of the Code of Federal Regulations Part 72 (10 CFR Part 72). Under these regulations, storage casks must be evaluated to verify that they meet various criteria, including acceptable thermal performance requirements. The purpose of the evaluation described in this paper is to establish the effectiveness of a medium-effort modeling approach and associated simplifying assumptions in closely approximating spent fuel cask component temperature distributions. This predictive evaluation is performed with the ANSYS® code, and is applicable to externally cooled cask designs. The results are compared against experimental measurements and predictions of the COBRA-SFS finite-difference code developed at Pacific Northwest National Laboratory.
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ASME 2007 Pressure Vessels and Piping Conference
July 22–26, 2007
San Antonio, Texas, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4285-1
PROCEEDINGS PAPER
Benchmarking of a Thermal Finite Element Approximation Scheme for Externally Cooled Spent Fuel Storage Casks
Christopher S. Bajwa,
Christopher S. Bajwa
U.S. Nuclear Regulatory Commission, Rockville, MD
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Ian F. Spivack
Ian F. Spivack
U.S. Nuclear Regulatory Commission, Rockville, MD
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Christopher S. Bajwa
U.S. Nuclear Regulatory Commission, Rockville, MD
Ian F. Spivack
U.S. Nuclear Regulatory Commission, Rockville, MD
Paper No:
PVP2007-26735, pp. 529-538; 10 pages
Published Online:
August 20, 2009
Citation
Bajwa, CS, & Spivack, IF. "Benchmarking of a Thermal Finite Element Approximation Scheme for Externally Cooled Spent Fuel Storage Casks." Proceedings of the ASME 2007 Pressure Vessels and Piping Conference. Volume 7: Operations, Applications and Components. San Antonio, Texas, USA. July 22–26, 2007. pp. 529-538. ASME. https://doi.org/10.1115/PVP2007-26735
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