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 - BREAK TEST OF FULL SCALE LEAD RUBBER BEARINGS FOR NUCLEAR FACILITIES, PART3 FINITE ELEMENT ANALYSIS MODEL FOR BREAK TEST-
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DEVELOPMENT OF EVALUATION METHOD FOR SEISMIC ISOLATION SYSTEMS OF NUCLEAR POWER FACILITIES - BREAK TEST OF FULL SCALE LEAD RUBBER BEARINGS FOR NUCLEAR FACILITIES, PART3 FINITE ELEMENT ANALYSIS MODEL FOR BREAK TEST-

机译:核动力设施隔震系统评估方法的发展-核设施用全铅橡胶轴承的断裂试验,第3部分断裂试验的有限元分析模型

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摘要

In the previous report, other part of this series of papers (Imaoka et al. (2015) and Nakayama et al. (2015)), break test results of full-scale lead rubber bearing (LRB) were shown. In this report, we propose finite element analysis (FEA) model which can trace the break test results for the purpose of prediction of LRB break characteristics. In the case of modelling FEA for rubber bearings, selection of material model for rubber is important. As a rubber material model, we select hyper-elastic model which can represent the softening under tri-axial tensile deformation. First, details of proposed FEA model are shown. Second, we show the validity of proposed model by comparing with break test results of relation between shear/tensile stress and shear/tensile strain. Finally, breaking criteria of LRB is suggested.
机译:在之前的报告中,该系列论文的其他部分(Imaoka等人(2015年)和Nakayama等人(2015年))显示了全尺寸铅橡胶轴承(LRB)的断裂试验结果。在本报告中,我们提出了有限元分析(FEA)模型,该模型可以跟踪断裂测试结果,以预测LRB断裂特性。对于橡胶轴承的FEA建模,选择橡胶的材料模型很重要。作为橡胶材料模型,我们选择能代表三轴拉伸变形下的软化作用的超弹性模型。首先,显示了拟议的FEA模型的详细信息。其次,通过与剪切/拉伸应力与剪切/拉伸应变之间关系的断裂试验结果进行比较,我们证明了所提模型的有效性。最后,提出了LRB的突破标准。

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  • 会议地点 Manchester(GB)
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    Infrastructure Products Development Department Bridgestone Corporation Japan;

    Fellow Infrastructure Products Development Department Bridgestone Corporation Japan;

    Central Research Institute of Electric Power Industry (CRIEPI) Japan;

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

    Structure No.l Lab. Strength Research Dept. Research Innovation Center Mitsubishi Heavy Industries Ltd. Japan;

    Plant Design Engineering Dept. Isogo Nuclear Engineering Center Toshiba Corporation Power Systems Company Japan;

    Structural Engineering Nuclear Power Department Kajima Corporation Japan;

    Nuclear Power Plant Arch. Eng. Section Civil Arch. Dept. Chubu Electric Power Co. Inc. Japan;

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