Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Seismic analysis of free-standing spent-fuel dry storage cask considering soil-concrete pad-cask interaction

  • Seungpil Kim (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute) ;
  • Sang Soon Cho (Radwaste Transportation and Storage Research Team, Korea Atomic Energy Research Institute)
  • Received : 2024.03.11
  • Accepted : 2024.06.05
  • Published : 2024.10.25
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Abstract

This paper presents a seismic analysis method that can evaluate a very large number of cases for the free standing dry storage cask by proposing a methodology that has short analysis time as well as accuracy. This study also performed a seismic analysis of a dry storage facility with multiple casks to show a tip-over phenomenon from earthquake accident conditions. The earthquake accident condition is long-term event that occur during about 20 s long, and lots of seismic analysis cases should be performed to consider various real conditions because the free-standing spent-fuel dry storage cask has many nonlinear responses. The soil-concrete pad-cask interaction was considered in the seismic analysis and finite element model was made using concrete pad, soil and cask models. In the reinforced concrete pad, the rebar was excluded to reduce the analysis time, but the thickness was corrected to maintain the bending rigidity. Additionally, the analysis time reduced by modeling the cask as a rigid body rather than a flexible body. 35-cases of seismic analysis were performed to determine a tip-over phenomenon from each earthquake. The analysis revealed that no tip-over phenomenon of the cask was observed in all analyses from 0.2 g to 0.6 g, however the tip-over of the cask were observed from 0.8 g with friction coefficients of 0.8 and 1.0.

Keywords

Acknowledgement

This study was supported by the Institute for Korea Spent Nuclear Fuel (iKSNF) and National Research Foundation of Korea (NRF) (Ministry of Science and ICT, MSIT; grant No. 2021M2E1A1085229).

References

  1. M. Hanifehzadeh, B. Gencturk, R. Mousavi, A numerical study of spent nuclear fuel dry storage systems under extreme impact loading, Eng. Struct. 161 (2018) 68-81, https://doi.org/10.1016/j.engstruct.2018.01.068.
  2. S. Lee, B. Amomani, D.C. Jang, H.G. Kang, A PSA framework for an interim dry storage facility subjected to an Aircraft Crash, in: Vol. 1 PHM Society Asia Pacific Conference, 2017.
  3. M.E. Ebad Sichani, J.E. Padgett, V. Bisadi, Probabilistic seismic analysis of concrete dry cask structures, Struct. Saf. 73 (2018) 87-98, https://doi.org/10.1016/j.strusafe.2018.03.001.
  4. K. Shirai, K. Hirata, T. Saegusa, Experimental studies of FreeStanding spent fuel storage cask subjected to strong earthquakes, in: Transactions of SMiRT 17, Prague, Czech Republic, August 17-22, 2003.
  5. Y.Y. Ko, S.Y. Hsu, C.H. Chen, Analysis for seismic response of dry storage facility for spent fuel, Nucl. Eng. Des. 239 (2009) 158-168, https://doi.org/10.1016/j.nucengdes.2008.09.006.
  6. V.K. Luk, B.W. Spencer, I.P. Lam, R.A. Dameron, Parametric Evaluation of Seismic Behavior of Freestanding Spent Fuel Dry Cask Storage Systems, Sandia National Laboratories, Albuquerque, New Mexico, 2005, pp. SAND2004-SAND5794P. Report No. NUREG/CR-6865.
  7. W.M. Morrow, E.D. Uldrich, Propsed criteria for the stability in earthquakes of nuclear-material shipping casks, Idaho National Engineering Laboratory, Idaho Falls (1995).
  8. M.J. S, P.A. Cox, A.H. Chowdhury, Tip-over analysis of the HI-STORM dry storage cask system., Idaho national engineering laboratory, in: 17th International Conference on Structural Mechanics in Reactor Technology, 2003. Prague, Czech Republic.
  9. L. Ibarra, D. Sanders, C. Pantelides, H. Yang, Seismic Performance of Dry Casks Storage for Long-Term Exposure, Battelle Energy Alliance, LLC, Idaho Falls, ID (United States), 2016. No. 12-3756.
  10. Dassault Systemes, ABAQUS 6.14, Documentation, Simulia Co., Providence, Rhode Island, 2015.
  11. US Nuclear Regulatory Commission, Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities (NUREG-2215), United States Nuclear Regulatory Commission, Washington, District of Columbia, 2020.
  12. U. S., Nuclear regulatory commission, in: Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants, Second Revision, Nuclear Regulatory Commission, Washington, District of Columbia, 2014. RG1.60.
  13. US Nuclear Regulatory Commission, Parametric Evaluation of Seismic Behavior of Freestanding Spent Fuel Dry Cask Storage Systems (NUREG/CR-6865), United States Nuclear Regulatory Commission, Washington, District of Columbia, 2004.
  14. Y. Ichihara, N. Nakamura, H. Moritani, B. Choi, A. Nishida, 3D FEM soil-structure interaction analysis for Kashiwazaki-Kariwa nuclear power plant considering soil separation and sliding, Front. Built Environ. 7 (2021) 676408, https://doi.org/10.3389/fbuil.2021.676408.
  15. EPRI, The Effects of Target Hardness on the Structural Design of Concrete Storage Pds for Spent-Fuel Casks (EPRI NP-4830), Egyptian Petroleum Research Institute, California, 1986.
  16. I. Hunter, TN-32 FSAR Update Per 10CFR72, United States Nuclear Regulatory Commission, 2002.
  17. S.S. Cho, K.-S. Seo, W.-S. Choi, S.-H. Yu, Y.-Y. Yang, Development of Assessment Technology for Tip-Over and Retrievavility of Spent Fuel Dry Storage Cask (KAERI/CR-670/2017), KAERI, Daejeon, Korea, 2017.
  18. US Nuclear Regulatory Commission, Development of Criteria for Seismic Review of Selected Nuclear Power Plants (NUREG/CR-0098), United States Nuclear Regulatory Commission, Washington, District of Columbia, 1978.
  19. US Nuclear Regulatory Commission, Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard- and Risk-Consistent Ground Motion Spectra Guidelines (NUREG/CR-6728), United States Nuclear Regulatory Commission, Washington, District of Columbia, 2001.