核电站结构在远场地震动下的创新性概率易损性研究

Q4 Engineering
Bhairav Thakur, A. Desai, H. Shah, Gondaliya Kaushik
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引用次数: 0

摘要

结构的地震易损性是给定地震危险等级下的条件倒塌破坏。本研究为印度苏拉特核电站(NPP)反应堆安全壳结构(RCS)的抗震性能和损伤评估建立了一个可接受的地震等级。采用有限元法对RCS模型进行了非线性研究。采用一系列非线性时程模拟对RCS穹顶顶部进行了观测。建立了RCS各烈度措施的概率地震需求模型。本研究总结了与核设施损伤分析有关的若干准则和技术。线性回归法利用增量动态分析结果生成易损性曲线。分析研究得出结论,核反应堆在0.87g RCS下有50%的几率轻微坍塌。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Innovative Probabilistic Vulnerability Investigation of Nuclear Power Plant Structures under Far-Field Ground Motion
A structure's seismic fragility is the conditional collapse damage for a given seismic hazard level. This study established an earthquake level acceptable for the seismic performance and damage evaluations of a nuclear power plant's (NPP) reactor containment structure (RCS) in Surat, India. The RCS model's nonlinear studies were conducted using the finite element method (FEM). A series of nonlinear time-history simulations were also applied to observe the top of the RCS dome. Probabilistic seismic demand models for each intensity measure (IM) of RCS were constructed (IM). This study summarises several guidelines and techniques related to the damage analysis of nuclear facilities. The linear regression method uses incremental dynamic analysis results to produce the fragility curve. The analytical studies concluded that the nuclear reactor has a 50 per cent chance of slightly collapsing at 0.87g of RCS.
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来源期刊
Disaster Advances
Disaster Advances 地学-地球科学综合
CiteScore
0.70
自引率
0.00%
发文量
57
审稿时长
3.5 months
期刊介绍: Information not localized
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