4.5 Article

Seismic response correlation coefficient for the structures, systems and components of the Korean nuclear power plant for seismic probabilistic safety assessment

期刊

ANNALS OF NUCLEAR ENERGY
卷 150, 期 -, 页码 -

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2020.107759

关键词

Seismic probabilistic safety assessment; Seismic correlation; Seismic response correlation; Nuclear power plants; Probabilistic seismic response analysis

资金

  1. Kyungpook National University Research Fund, 2019

向作者/读者索取更多资源

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.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.5
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据