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Joint Development of Seismic Capability Evaluation Technology for Degraded Structures and Components. Annual Report for Year 3 Task. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants-Illustrated using a Condensate Storage Tank

机译：退化结构与构件抗震能力评估技术的联合开发。第3年任务年度报告。核电厂退化结构和被动部件的脆弱性分析方法 - 使用冷凝水储罐进行说明

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The Korea Atomic Energy Research Institute (KAERI) is conducting a five-year research project to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). The KAERI research project includes three specific areas that are essential to seismic probabilistic risk assessment (PRA): (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. Since 2007, Brookhaven National Laboratory (BNL) has entered into a collaboration agreement with KAERI to support its development of seismic capability evaluation technology for degraded structures and components. The collaborative research effort is intended to continue over a five year period. The goal of this collaboration endeavor is to assist KAERI to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The research results of this multi-year collaboration will be utilized as input to seismic PRAs.

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Nie, J.; Braverman, J.; Hofmayer, C.;
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年度 2010
页码 1-231
总页数 231
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Nuclear power plants ; Risk assessment ; Steels ; Aging ; BNL ; Carbon ; Low alloy steels ; Stainless steels ; Storage tanks ; Seismic design ; Earthquake engineering;

机译：核电厂;风险评估;钢;老化; BNL;碳;低合金钢;不锈钢;储罐;抗震设计;地震工程;

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1. Determining seismic fragility of structures and components in nuclear power plants using multiple ground motion parameters - Part Ⅰ: Methodology [J] . Cai Zhen, Xie Wei-Chau, Pandey Mahesh D., Nuclear Engineering and Design . 2018,第AUGa期

机译：使用多个地面运动参数确定核电厂结构和组件的地震脆性-第一部分：方法论
2. Development and analysis of seismic experience database of structures,systems and components in nuclear power plants based on investigation reports and maintenance records [J] . Morita Ryo, Saito Kiyoshi, Yuyama Ayumi Nuclear Engineering and Design . 2021,第Apra期

机译：基于调查报告和维护记录的核电厂结构，系统和组件地震体验数据库的开发与分析
3. Degradation assessment of structures and passive components at nuclear power plants [J] . J.I. Braverman, C.A. Miller, C.H. Hofmayer, Nuclear Engineering and Design . 2004,第1a3期

机译：核电厂结构和无源组件的退化评估
4. SEISMIC FRAGILITY ANALYSIS OF A CONDENSATE STORAGE TANK WITH MULTIPLE UNCERTAIN DEGRADATION SCENARIOS [C] . Jinsuo R. Nie, Joseph I. Braverman, Charles H. Hofmayer, International conference on nuclear engineering;ASME power conference . 2012

机译：具有多个不确定降解场景的冷凝水储罐的易碎性分析
5. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants - Illustrated using a Condensate Storage Tank [O] . Nie, J., Braverman, J., Hofmayer, C., 2010

机译：核电厂退化结构和被动构件的脆弱性分析方法 - 用凝结水储罐说明

Joint Development of Seismic Capability Evaluation Technology for Degraded Structures and Components. Annual Report for Year 3 Task. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants-Illustrated using a Condensate Storage Tank

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