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Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask KCI 등재 SCOPUS

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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

Because most spent nuclear fuel storage casks have been designed for low burnup fuel, a safety-significant high burnup dry storage cask must be developed for nuclear facilities in Korea to store the increasing high burnup and damaged fuels. More than 20% of fuels generated by PWRs comprise high burnup fuels. This study conducted a structural safety evaluation of the preliminary designs for a high burnup storage cask with 21 spent nuclear fuels and evaluated feasible loading conditions under normal, off-normal, and accident conditions. Two types of metal and concrete storage casks were used in the evaluation. Structural integrity was assessed by comparing load combinations and stress intensity limits under each condition. Evaluation results showed that the storage cask had secured structural integrity as it satisfied the stress intensity limit under normal, off-normal, and accident conditions. These results can be used as baseline data for the detailed design of high burnup storage casks.

목차
1. Introduction
2. Dry Storage Cask for High Burnup andDamaged Fuel
3. Specifications of the Storage Cask
    3.1 Canister
    3.2 Metal Storage Cask
    3.3 Concrete Storage Cask
4. Allowable Stress
5. Structural Analysis Model
6. Loading Conditions
7. Structural Analysis Results
8. Conclusion
Conflict of Interest
Acknowledgements
REFERENCES
저자
  • Taehyung Na(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Youngoh Lee(Korea Nuclear Engineering & Service, 65, Myeongdal-ro, Seocho-gu, Seoul 06667, Republic of Korea)
  • Yeji Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Donghee Lee(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Taehyeon Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Kiyoung Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Yongdeog Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea) Corresponding author