强震作用下核电站反应堆厂房结构的抗震性能分析  

Seismic performance analyses of reactor building structures in nuclear power plant under strong earthquake motions

作　　者：郭婧[1] 方火浪[1] 张轶群[1] 曾泽斌[2] 

机构地区：[1]浙江大学建筑工程学院,浙江杭州310058 [2]浙江理工大学机械与自动控制学院,浙江杭州310018

出　　处：《地震工程与工程振动》2016年第6期11-21,共11页Earthquake Engineering and Engineering Dynamics

基　　金：国家自然科学基金项目(41502268)~~

摘　　要：以位于强震区的国外某核电站为研究对象,建立考虑弯剪耦合非线性变形特性的反应堆厂房结构的集中质量模型,运用Open Sees软件对反应堆厂房结构进行动力弹塑性时程分析,研究反应堆厂房结构在设计基准地震和超设计基准地震作用下的地震反应特性,并且对反应堆厂房结构的抗震性能和抗震安全裕度进行评价。结果表明,在设计基准地震作用下,反应堆厂房结构变形较小,基本上处于弹性状态。在2倍设计基准地震作用下,反应堆厂房结构变形较大,个别构件呈现较为明显的非线性变形行为,特别是预应力混凝土安全壳底部的剪切变形已进入屈服状态。虽然在2倍设计基准地震作用下,反应堆厂房结构的部分构件发生开裂及屈服,但主体结构仍保持整体完好。因此,该反应堆厂房结构可满足抗震安全性要求并具有一定的抗震安全裕度。This study focuses on the seismic capacity evaluation of the reactor building structures in a nuclear power plant located in the strong earthquake area abroad. A lumped mass model considering nonlinear shear-flexure inter- action behaviors is established and its dynamic elasto-plastic time history analyses are carried out by use of the open-source seismic simulation software OpenSees. The seismic response performances and safety margins of the re- actor building structures are investigated under the design and beyond-design basis earthquake motions. The results show that the reactor building structures generate relatively small deformations and are basically in elastic state un- der the design basis earthquake motion. However, the structures generate relatively large de formations and some parts of structures characterize obvious nonlinear deformation behaviors under two times the design basis earthquake motion, especially the bottom of the prestressed concrete containment vessel reaches to the yielding state in the shear deformation. Although cracking and yielding in some structures appear under two times the design basis earthquake motion, the reactor building structures still remain integral as a whole. Therefore, it can be concluded that the re- actor building structures meet the seismic safety requirements and have a certain degree of seismic safety margin.

关 键 词：核电站 反应堆厂房 集中质量模型 抗震性能 

分 类 号：TU271.5[建筑科学—建筑设计及理论] TU352.1