首页> 外文会议>International Conference on Structural Mechanics in Reactor Technology >DEVELOPMENT OF EVALUATION METHOD FOR SEISMIC ISOLATION SYSTEMS OF NUCLEAR POWER FACILITIES - SEISMIC FRAGILITY EVALUATION OF EQUIPMENT-
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DEVELOPMENT OF EVALUATION METHOD FOR SEISMIC ISOLATION SYSTEMS OF NUCLEAR POWER FACILITIES - SEISMIC FRAGILITY EVALUATION OF EQUIPMENT-

机译:核动力设施地震隔离系统评估方法的发展-设备地震易损性评估-

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This paper provides a part of series of 'Development of Evaluation Method For Seismic Isolation Systems of Nuclear Power Facilities'. This part describes the seismic fragility evaluation for equipment of the seismic isolated plants. In order to respond the regulatory requirement of residual risk evaluation, a research on residual risk evaluation of the seismic isolated plants is proceeding as a part of the Japan national project of seismic isolation. As efforts for this research, realistic capacities of seismic isolators are studied by braking tests of full-scale seismic isolation systems and of crossover piping are studied by shaking tests of scaled model and static tests by simultaneous loads of in-plane and out-of-plane. Fragilities of the seismic isolators and crossover piping are evaluated based on the results of these studies. Seismic response characteristics of the seismic isolated buildings show strong non-linearity and large displacement because of the vibration characteristic of the seismic isolation system. Therefore, response characteristics specific to the seismic isolated buildings such as non-linear response and relative displacement between isolated building and non-isolated building shall be considered in the fragility evaluation methodology for equipment of the seismic isolated plants. This paper focuses on the seismic fragility evaluation of equipment of the seismic isolated plants considering the relative displacement and non-linear response of the buildings. Representative equipment of isolated plants are selected and fragility evaluations of the equipment are performed based on the results of the response analysis of buildings and crossover piping. Result of seismic PRA using fragility values obtained in this study is reported in other part of this series of papers.
机译:本文提供了“核电设施隔震系统评估方法的发展”系列的一部分。本部分描述了地震隔离工厂设备的地震易损性评估。为了满足残留风险评估的法规要求,作为日本国家地震隔离项目的一部分,正在进行对地震隔离工厂的残留风险评估的研究。作为这项研究的工作,通过全尺寸隔震系统的制动测试研究了隔震器的实际能力,并通过比例模型的振动测试和跨面内和外加荷载同时进行的静态测试研究了隔震管道的实际能力。飞机。基于这些研究的结果,对地震隔离器和交叉管道的脆弱性进行了评估。由于隔震系统的振动特性,隔震建筑物的地震响应特性表现出很强的非线性和大位移。因此,在地震隔离工厂设备的脆性评估方法中,应考虑地震隔离建筑物的特定响应特性,例如非线性响应以及隔离建筑物与非隔离建筑物之间的相对位移。考虑到建筑物的相对位移和非线性响应,本文重点研究了地震隔离工厂设备的地震易损性评估。选择隔离工厂的代表性设备,并根据建筑物和交叉管道的响应分析结果对设备进行脆弱性评估。本系列文章的其他部分报告了使用本研究中获得的脆性值进行地震PRA的结果。

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  • 会议地点 Manchester(GB)
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    Structural Seismic Engineering Section Nuclear Plant Designing Department Nuclear Energy Systems Division Energy Environment Mitsubishi Heavy Industries Ltd. Japan;

    Nuclear Plant Designing Department Nuclear Energy Systems Division Energy Environment Mitsubishi Heavy Industries Ltd. Japan;

    Piping Structural Design Group Structural Safety Engineering Department Plant Development Promotive Division MHI Nuclear Engineering Company Ltd. Japan;

    Aseismic Structure Technology Group Plant Design Engineering Dept. Isogo Nuclear Engineering Center Toshiba Corporation Power Systems Company Japan;

    Aseismic Engineering Sec Nuclear Plant Engineering Dept. Hitachi-GE Nuclear Energy Ltd Japan;

    Design Engineering Group Nuclear Power Dept. Nuclear Power Div. Chubu Electric Power Co. Inc. Japan;

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