4.5 Article

Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components

期刊

ENERGIES
卷 14, 期 11, 页码 -

出版社

MDPI
DOI: 10.3390/en14113269

关键词

nuclear component; seismic fragility analysis; seismic capacity; HCLPF; strain-based seismic criteria; ductile fracture; fatigue-induced failure; inelastic seismic time history analysis

资金

  1. Ministry of Trade, Industry and Energy through KETEP (Korea Institute of Energy Technology Evaluation Planning) [20181510102380]
  2. Korea Evaluation Institute of Industrial Technology (KEIT) [20181510102380] Funding Source: Korea Institute of Science & Technology Information (KISTI), National Science & Technology Information Service (NTIS)

向作者/读者索取更多资源

The study aims to investigate the feasibility of seismic fragility analysis with strain-based failure modes for nuclear metal components retaining pressure boundary, in order to enhance high confidence of low probability of failure capacity potentially contained in the conservative seismic design criteria. The study also explores the possibility of using seismic FA as an alternative seismic design rule for beyond-design-basis earthquakes.
The main purpose of this study is to investigate the feasibility of the seismic fragility analysis (FA) with the strain-based failure modes for the nuclear metal components retaining pressure boundary. Through this study, it is expected that we can find analytical ways to enhance the high confidence of low probability of failure (HCLPF) capacity potentially contained in the conservative seismic design criteria required for the nuclear metal components. Another goal is to investigate the feasibility of the seismic FA to be used as an alternative seismic design rule for beyond-design-basis earthquakes. To do this, the general procedures of the seismic FA using the inelastic seismic analysis for the nuclear metal components are investigated. Their procedures are described in detail by the exampled calculations for the surge line nozzles connecting hot leg piping and the pressurizer, known as one of the seismic fragile components in NSSS (Nuclear Steam Supply System). To define the seismic failure modes for the seismic FA, the seismic strain-based design criteria, with two seismic acceptance criteria against the ductile fracture failure mode and fatigue-induced failure mode, are used in order to reduce the conservatism contained in the conventional stress-based seismic design criteria. In the exampled calculation of the inelastic seismic strain response beyond an elastic regime, precise inelastic seismic analyses with Chaboche's kinematic and Voce isotropic hardening material models are used. From the results of the seismic FA by the probabilistic approach for the exampled target component, it is confirmed that the approach of the strain-based seismic FA can extract the maximum seismic capacity of the nuclear metal components with more accurate inelastic seismic analysis minimizing the number of variables for the components.

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