4.6 Article

Preliminary strong ground motion simulation at seismic stations within nuclear power plant sites in South Korea by a scenario earthquake on the causative fault of 2016 Gyeongju earthquake

Journal

NUCLEAR ENGINEERING AND TECHNOLOGY
Volume 54, Issue 7, Pages 2529-2539

Publisher

KOREAN NUCLEAR SOC
DOI: 10.1016/j.net.2022.01.017

Keywords

Stochastic; Empirical Green's function; Strong ground motion simulation; Gyeongju earthquake; Adjustment factor

Funding

  1. Nuclear Safety Research Pro- gram through the Korea Foundation of Nuclear Safety
  2. Nuclear Safety and Security Commission of the Republic of Korea [1705010-0521-SB130, 1805020-0421-CG10 0]
  3. Nuclear Safety & Security Commission (NSSC), Republic of Korea [1705010-0521-SB130] Funding Source: Korea Institute of Science & Technology Information (KISTI), National Science & Technology Information Service (NTIS)

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Stochastic and EGF methods were applied to simulate strong ground motions at seismic stations within nuclear power plant sites in South Korea. The results show similar response spectra by the two methods, slightly exceeding the standard design response spectra.
Stochastic and an empirical Green's function (EGF) methods are preliminarily applied to simulate strong ground motions (SGMs) at seismic stations within nuclear power plant (NPP) sites in South Korea by an assumed large earthquake with MW6.5 (scenario earthquake) on the causative fault of the 2016 Gyeongju earthquake with MW5.5 (mainshock). In the stochastic method, a ratio of spectral amplitudes of observed and simulated waveforms for the mainshock is assumed to be an adjustment factor. In the EGF method, SGMs by the mainshock are simulated assuming SGMs by the 2016 Gyeongju earthquake with MW5.0 (foreshock) as the EGF. To simulate SGMs by the scenario earthquake, a ratio of fault length to width is assumed to be 2:1 in the stochastic method, and SGMs by the mainshock are assumed to be EGF in the EGF method. The results are similar based on a bias of the simulated response spectra by the two methods, and the simulated response spectra by the two methods exceeded commonly standard design response spectra anchored at 0.3 g of NPP sites slightly at a frequency band above 4 Hz, but considerable attention to interpretation is required since it is an indirect comparison. ?? 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

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