EPR核电站内安全壳筒体施工全过程力学性态分析  

THE WHOLE PROCESS CONSTRUCTION MECHANICAL ANALYSIS OF CONTAINMENT CYLINDER FOR NUCLEAR POWER PLANT

作　　者：卢海陆[1] 李政 谭俊 金晓飞[1] 

机构地区：[1]中国建筑股份有限公司技术中心,北京101300 [2]中建二局核电建设分公司,广东深圳518034

出　　处：《工业建筑》2013年第5期24-27,78,共5页Industrial Construction

基　　金：中国建筑股份有限公司资助课题(CSCEC-2008-Z-17)

摘　　要：安全壳作为第三代核电站提供保护、密闭等功能的重要部件,直接关系到核电站的安全运营。以某核电站为工程依托,基于大型有限元通用软件ANSYS,分析了安全壳内壳钢衬里在安装积累精度、分段高度、新浇筑混凝土对钢衬里侧压力及风荷载作用等施工过程因素对结构力学性态的影响,得出了钢衬里、混凝土筒体在已有分区高度下的结构最大应力值及钢衬里的最大径向位移等,并得出了新浇筑混凝土侧压力对结构的影响最大,及施工模拟中必须考虑钢衬里的二阶效应等结论。针对核电内壳筒体具体结构,给出了网格划分的关键技术和步骤,为以后核电站内壳分析提供参考。The containment which provides protection, sealing and other functions is an important component of thirdgeneration nuclear power plants （European Pressurised Reactor, EPR）. Based on a nuclear power plant project, by finite software ANSYS it was analyzed the effects of the following factors on structural mechanical behavior under construction, such as accumulation accuracy of liner installation, modular construction height, pouring concrete lateral pressure and wind loads etc. The maximum radial displacement of the liner and the maximum stress of containment were got; and the pouring concrete lateral pressure of the concrete had the greatest impact on the structure during the construction. In addition, the second-order effects must be taken into account in the simulation. For the nuclear shell cylinder structure, the key technologies and steps of the mesh division were also given, which provided a reference for future analysis of containment.

关 键 词：EPR 钢衬里 网格划分 模块化施工 

分 类 号：TL364.3[核科学技术—核技术及应用]