节点文献
核电站安全壳隔震可靠度分析
【机构】 哈尔滨工业大学; 中国地震局工程力学研究所;
【摘要】 隔震技术已广泛应用于建筑结构且有很好的效果,但对于核电站这一类重要建筑,隔震技术的应用还需做专门的研究。本文研究了隔震后核电站安全壳的可靠度,利用ANSYS有限元软件建立了核电站安全壳三维实体模型,应用反应谱分析方法与蒙特卡罗分析方法给出了核电站安全壳在隔震和不隔震下混凝土开裂的失效概率。此外,文中还给出了隔震层位移超限的失效概率。结果表明,通过合理的选择隔震支座,核电站安全壳隔震可大大提高其安全度。
【Abstract】 Isolation technology has been widely used in general building and has good effect, but the application of isolation still needs to be done for nuclear power plant of this important building. In this paper, a 3D model of nuclear containment has been built by using the finite element analysis software ANSYS. The failure probability of concrete cracking for the nuclear power plant containment with isolation or without has been investigated using the response spectrum method combined with the Monte Carlo method. In addition, the probability of isolation layer’s displacement exceeding the limit was also presented. It was noted that the isolation of nuclear containment greatly improves its safety through selecting the isolation devices rationally.
【Key words】 containment; isolation; spectrum; failure probability; Monte Carlo; response surface method;
- 【会议录名称】 第十七届全国反应堆结构力学会议论文集
- 【会议名称】第十七届全国反应堆结构力学会议
- 【会议时间】2012-10-15
- 【会议地点】中国上海
- 【分类号】TU352.12
- 【主办单位】中国力学学会反应堆结构力学专业委员会