Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel

  • Taehyung Na (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Youngoh Lee (Korea Nuclear Engineering & Service) ;
  • Taehyeon Kim (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Yongdeog Kim (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd.)
  • Received : 2023.06.20
  • Accepted : 2023.08.07
  • Published : 2023.12.30
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Abstract

A transfer cask serves as the container for transporting and handling canisters loaded with spent nuclear fuels from light water reactors. This study focuses on a cylindrical transfer cask, standing at 5,300 mm with an external diameter of 2,170 mm, featuring impact limiters on the top and bottom sides. The base of the cask body has an openable/closable lid for loading canisters with storage modules. The transfer cask houses a canister containing spent nuclear fuels from lightweight reactors, serving as the confinement boundary while the cask itself lacks the confinement structure. The objective of this study was to conduct a structural analysis evaluation of the transfer cask, currently under development in Korea, ensuring its safety. This evaluation encompasses analyses of loads under normal, off-normal, and accident conditions, adhering to NUREG-2215. Structural integrity was assessed by comparing combined results for each load against stress limits. The results confirm that the transfer cask meets stress limits across normal, off-normal, and accident conditions, establishing its structural safety.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government the Ministry of Trade, Industry and Energy (No. 2021171020001B).

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