TY - JOUR
T1 - Seismic performance assessment of NPP concrete containments considering recent ground motions in South Korea
AU - Kim, Chanyoung
AU - Cha, Eun Jeong
AU - Shin, Myoungsu
N1 - Funding Information:
This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (No. 20201510100020 , Research on analysis of earthquake & fault characteristics and seismic performance improvement to respond against earthquake hazards).
Publisher Copyright:
© 2021 Korean Nuclear Society
PY - 2022/1
Y1 - 2022/1
N2 - Seismic fragility analysis, a part of seismic probabilistic risk assessment (SPRA), is commonly used to establish the relationship between a representative property of earthquakes and the failure probability of a structure, component, or system. Current guidelines on the SPRA of nuclear power plants (NPPs) used worldwide mainly reflect the earthquake characteristics of the western United States. However, different earthquake characteristics may have a significant impact on the seismic fragility of a structure. Given the concern, this study aimed to investigate the effects of earthquake characteristics on the seismic fragility of concrete containments housing the OPR-1000 reactor. Earthquake time histories were created from 30 ground motions (including those of the 2016 Gyeongju earthquake) by spectral matching to the site-specific response spectrum of Hanbit nuclear power plants in South Korea. Fragility curves of the containment structure were determined under the linear response history analysis using a lumped-mass stick model and 30 ground motions, and were compared in terms of earthquake characteristics. The results showed that the median capacity and high confidence of low probability of failure (HCLPF) tended to highly depend on the sustained maximum acceleration (SMA), and increase when using the time histories which have lower SMA compared with the others.
AB - Seismic fragility analysis, a part of seismic probabilistic risk assessment (SPRA), is commonly used to establish the relationship between a representative property of earthquakes and the failure probability of a structure, component, or system. Current guidelines on the SPRA of nuclear power plants (NPPs) used worldwide mainly reflect the earthquake characteristics of the western United States. However, different earthquake characteristics may have a significant impact on the seismic fragility of a structure. Given the concern, this study aimed to investigate the effects of earthquake characteristics on the seismic fragility of concrete containments housing the OPR-1000 reactor. Earthquake time histories were created from 30 ground motions (including those of the 2016 Gyeongju earthquake) by spectral matching to the site-specific response spectrum of Hanbit nuclear power plants in South Korea. Fragility curves of the containment structure were determined under the linear response history analysis using a lumped-mass stick model and 30 ground motions, and were compared in terms of earthquake characteristics. The results showed that the median capacity and high confidence of low probability of failure (HCLPF) tended to highly depend on the sustained maximum acceleration (SMA), and increase when using the time histories which have lower SMA compared with the others.
KW - Earthquake characteristics
KW - NPP concrete Containment
KW - Seismic fragility analysis
KW - Seismic probabilistic risk assessment
KW - Spectral-matched time history
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U2 - 10.1016/j.net.2021.07.035
DO - 10.1016/j.net.2021.07.035
M3 - Article
AN - SCOPUS:85111641083
SN - 1738-5733
VL - 54
SP - 386
EP - 400
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 1
ER -