DOI QR코드

DOI QR Code

Seismic analysis of a steam generator for Gyeongju and Pohang earthquakes

  • 투고 : 2022.09.26
  • 심사 : 2023.01.24
  • 발행 : 2023.05.25

초록

Safety qualification of a steam generator is a crucial issue related to faulted condition design loads, including earthquake loads, and it should be ensured that the structural integrity of a steam generator does not exceed its design load. Using data from the Gyeongju and Pohang earthquakes, the two most powerful recorded seismic events in Korea, seismic analyses of a typical steam generator are conducted in this study. The modal characteristics are used to develop an input deck for these analyses. With a time history analysis, the responses of the steam generator in the event of an earthquake are obtained. In particular, the displacement, velocity, and acceleration responses are obtained in the time domain, with these outcomes then used for a detailed structural analysis as part of the ensuing assessment. The response spectra are also generated to determine the response characteristics in the frequency domain, focusing on the response comparisons between the Gyeongju and Pohang earthquakes. Structural integrity can be ensured by performing additional analysis using results obtained from the time history analysis considering the input excitations of various earthquakes considered in the design.

키워드

과제정보

This work was supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea. (No. 1805005).

참고문헌

  1. IAEA, Seismic Design for Nuclear Installations, Specific Safety Guide No. SSG-67, International Atomic Energy Agency, Vienna, Austria, 2021.
  2. M.J. Jhung, Y. Choi, C. Oh, Dynamic response of a fuel assembly for a KSNP design earthquake, Nucl. Eng. Technol. 54 (2022) 3353-3360. https://doi.org/10.1016/j.net.2022.03.027
  3. M.J. Jhung, Y. Choi, C. Oh, Earthquake response of a core shroud for APR1400, Nucl. Eng. Technol. 53 (2021) 2716-2727. https://doi.org/10.1016/j.net.2021.02.007
  4. USNRC, ASME code class 1,2, and 3 components and component supports, and core support structures, Standard Review Plan 3 (9) (2007), 3, Revision 2, US Nuclear Regulatory Commission, Washington, D.C.
  5. K. Jin, J. Lee, K.-S. Lee, J.B. Kyung, Y.-S. Kim, Earthquake damage and related factors associated with the 2016 ML = 5.8 Gyeongju earthquake, southeast Korea, Geosci. J. 24 (2020) 141-157. https://doi.org/10.1007/s12303-019-0024-9
  6. http://necis.kma.go.kr/.
  7. K.-H. Kim, J.-H. Ree, Y. Kim, S. Kim, S.Y. Kang, W. Seo, Assessing whether the 2017 MW 5.4 Pohang earthquake in South Korea was an induced event, Science 360 (6392) (2018) 1007-1009. https://doi.org/10.1126/science.aat6081
  8. https://thediplomat.com/2019/12/the-social-fallout-from-pohangs-man-made-earthquake.
  9. ANSYS, ANSYS Mechanical APDL Theory Reference, ANSYS Inc., Canonsburg, PA, 2021. Release 2021 R1.
  10. R.G. Grimes, J.G. Lewis, H.D. Simon, A shifted Block Lanczos algorithm for solving sparse symmetric generalized eigenproblems, SIAM J. Matrix Anal. Appl. 15 (1) (1994) 228-272. https://doi.org/10.1137/S0895479888151111
  11. M.J. Jhung, Seismic Analysis of Steam Generator for APR1400 Using ANSYS, KINS/RR-2272, Korea Institute of Nuclear Safety, Daejeon, Korea, 2022.
  12. M.J. Jhung, W.G. Hwang, Seismic response of reactor vessel internals for Korean standard nuclear power plant, Nucl. Eng. Des. 165 (1996) 57-66. https://doi.org/10.1016/0029-5493(96)01204-6
  13. USNRC, Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components, Regulatory Guide 1.122, US Nuclear Regulatory Commission, Washington, D.C, 1978.
  14. M.J. Jhung, W.T. Kim, Y.H. Ryu, Dynamic characteristics of cylindrical shells considering fluid-structure interaction, Nucl. Eng. Technol. 41 (10) (2009) 1333-1346. https://doi.org/10.5516/NET.2009.41.10.1333
  15. M.J. Jhung, Y.H. Ryu, Study on dynamic response of mechanical component to earthquake, J. Nucl. Sci. Technol. 47 (11) (2010) 1065-1074. https://doi.org/10.1080/18811248.2010.9711671