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 Canister for Dry Storage System of PWR Spent Nuclear Fuels

  • 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.) ;
  • Donghee Lee (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd.)
  • Received : 2023.08.09
  • Accepted : 2023.09.13
  • Published : 2023.12.30
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Abstract

The aim of this study is to ensure the structural integrity of a canister to be used in a dry storage system currently being developed in Korea. Based on burnup and cooling periods, the canister is designed with 24 bundles of spent nuclear fuel stored inside it. It is a cylindrical structure with a height of 4,890 mm, an internal diameter of 1,708 mm, and an inner length of 4,590 mm. The canister lid is fixed with multiple seals and welds to maintain its confinement boundary to prevent the leakage of radioactive waste. The canister is evaluated under different loads that may be generated under normal, off-normal, and accident conditions, and combinations of these loads are compared against the allowable stress thresholds to assess its structural integrity in accordance with NUREG-2215. The evaluation result shows that the stress intensities applied on the canister under normal, off-normal, and accident conditions are below the allowable stress thresholds, thus confirming its structural integrity.

Keywords

Acknowledgement

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

References

  1. United States Nuclear Regulatory Commission. Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks, U.S. NRC Final Report, NUREG-2174 (2016).
  2. The American Society of Mechanical Engineers, Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder), NOG-1, ASME, NY (2020).
  3. United States Nuclear Regulatory Commission. Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities, U.S. NRC Final Report, NUREG-2215 (2020).
  4. U.S. Nuclear Regulatory Commission, Title 10, Code of Federal Regulations Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste, 10 CFR 72 (2020).
  5. United States Nuclear Regulatory Commission, Design Response Spectra for Seismic Design of Nuclear Power Plants, Revision 2, U.S. NRC Regulatory Guide 1.60 (2014).
  6. United States Nuclear Regulatory Commission, Damping Values for Seismic Design of Nuclear Power Plants, Revision 1, U.S. NRC Regulatory Guide 1.61 (2007).
  7. The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, 2019 Edition, ASME, NY (2019).
  8. The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendix F, 2019 Edition, ASME, NY (2019).
  9. The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NG, 2019 Edition, ASME, NY (2019).
  10. Dassault Systemes, ABAQUS 2017 (2017).
  11. The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section II, Part A-Ferrous Material Specifications, 2019 Edition, ASME, NY (2019).
  12. The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section II, Part D-Properties, 2019 Edition, ASME, NY (2019).