Journal
ANNALS OF NUCLEAR ENERGY
Volume 150, Issue -, Pages -Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2020.107759
Keywords
Seismic probabilistic safety assessment; Seismic correlation; Seismic response correlation; Nuclear power plants; Probabilistic seismic response analysis
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Funding
- Kyungpook National University Research Fund, 2019
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This study focused on the seismic response correlation coefficient for Korean NPPs to enhance the accuracy and reliability of safety assessments. By quantifying the correlation of seismic failure, correlation coefficient values applicable to auxiliary buildings were suggested.
The seismic probabilistic safety assessments of nuclear power plants (NPPs) conservatively assume that the correlation between the seismic failure to structures, systems, and components (SSCs) is independent or fully dependent. This, however, is an extreme assumption, and so a more appropriate seismic failure correlation should be considered for accurate safety assessments. Quantification of the correlation of seismic failure can be expressed with a correlation coefficient; to calculate this, correlation coefficients for both seismic response and seismic performance between SSCs are required. This study suggests a seismic response correlation coefficient for the OPR1000 Korean NPPs. To this end, a probabilistic seismic response analysis was performed considering the randomness and uncertainty of earthquakes and structures. Based on this in-structure spectrum, the seismic response correlation coefficient between the SSCs was derived and databased. Seismic response correlation coefficient values are also suggested that can easily be applied to auxiliary buildings of NPPs. (C) 2020 Elsevier Ltd. All rights reserved.
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