某核电厂LOCA下预应力混凝土安全壳响应规律初探  

Preliminary Study on Response Law of Prestressed Concrete Containment after LOCA in Certain NPP

作　　者：孙锋[1] 潘蓉[1] 柴国旱[1] 李亮[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《原子能科学技术》2015年第10期1815-1820,共6页Atomic Energy Science and Technology

基　　金：国家科技重大专项资助项目(2011ZX06002-10-16)

摘　　要：核电厂LOCA发生后,预应力混凝土安全壳结构内温度场分布具有明显的非线性特征,但现行的混凝土安全壳设计规范未对LOCA下温度和应力的组合作用提出具体的计算方法。基于用ANSYS程序建立的包含预应力钢束的混凝土安全壳结构的有限元模型,本文计算了LOCA下不同时刻安全壳壳壁内的温度场分布,并与理论值进行了比较,验证了计算模型的正确性。初步分析了高温、高压作用下安全壳结构变形的规律,总结了混凝土温度效应和预应力系统的作用,可为安全壳结构设计提供参考。After loss of coolant accident（LOCA）occurs in nuclear power plant,the temperature field distribution in prestressed concrete containment（PCC）is nonlinear significantly.However,the detailed calculation method combining temperature and pressure is not proposed in current PCC design code in China.In this paper,the finite element model for PCC including prestressed tendons was built by using ANSYS code and the temperature field under LOCA was calculated.The calculation results were compared with the theoretical results,and the accuracy of the proposed model was verified.The response law of PCC under high pressure and high temperature was preliminarily analysed,and the effects of temperature and prestressed tendons on PCC were concluded,which can provide reference to the concrete containment design.

关 键 词：核电厂 预应力混凝土安全壳 LOCA 温度场 响应规律 

分 类 号：TU35[建筑科学—结构工程]