摘要
日本福岛严重核事故后,超设计基准事故日益受到关注,核电厂在发生超设计基准事故(或严重事故)后,最关键的是要确保安全壳的完整性。基于某核电厂安全壳结构,建立包含预应力钢束的混凝土安全壳结构三维有限元模型,施加内压荷载进行非线性有限元分析,根据假定的破坏准则,给出了安全壳的极限承载能力,并与美国桑迪亚国家实验室的试验比较,初步分析了超压作用下安全壳整体结构及设备闸门局部区域的变形规律,安全壳超压破坏主要是由于设备闸门洞口附近的局部破坏所致。
Much attention was paid to the over design reference accident after the extraordinarily severe nuclear accident at Fukushima nuclear power plant in Japan. It is most important to keep structural integrity of containments for pressurized water reactor power plants after LOCA. The finite element model of the containment structure was built by using ANSYS code, the response laws of prestressed concrete containment under the over design reference internal pressure were analyzed. Through comparison between the load-deformation derived from the experimental results by SNL and the numerical bearing capacity test results based assumed failure criterion, the ultimate bearing capacity of the containment was given. Based on which, the prestressing system effects and deformation laws of the local zone of the equipment hatch were also analyzed. With the understanding of damage evolution, it is of key importance to keep the equipment hatch stability.
出处
《工业建筑》
CSCD
北大核心
2015年第9期13-16,63,共5页
Industrial Construction
基金
国家科技重大专项课题资助(2011ZX06002-10-16)
关键词
预应力混凝土安全壳
超设计压力
设备闸门
破坏准则
prestressed concrete containment vessel（ PCCV）
over designed pressure
equipment hatch
failure criterion
