CNP1000核电厂安全壳模型结构抗震安全分析  

ASEISMIC SAFETY ANALYSIS OF A CONTAINMENT VESSEL MODEL FOR CNP1000 NUCLEAR POWER PLANT

作　　者：段安[1] 钱稼茹[1] 

机构地区：[1]清华大学土木工程系结构工程与振动教育部重点实验室,北京100084

出　　处：《工程力学》2009年第4期153-157,196,共6页Engineering Mechanics

摘　　要：半球形穹顶、两根扶壁柱预应力混凝土安全壳是我国第三代一百万千瓦CNP1000先进核电厂的标志建筑物。为研究CNP1000核电厂安全壳的抗震安全,对安全壳1∶10模型结构进行了非线性有限元分析。非线性时程分析得到的结果与拟动力试验实测结果吻合较好,验证了所采用的计算模型和计算参数基本合理;静力非线性有限元分析结果表明,模型结构的静力极限水平力达到6670kN,为峰值加速度3g地震作用下最大水平剪力的4.55倍。CNP1000核电厂安全壳实体结构具有足够大的抗震安全储备。The pre-stressed concrete containment vessel （PCCV）, consisting of a semi-spherical dome, a cylinder and two buttresses, is the symbolic structure for CNP1000 nuclear power plant, developed in China in recent year. In order to evaluate the aseismic safety of the PCCV, non-linear analysis of a 1/10-scale PCCV model was carried out with MARC finite element program. The dynamic non-linear analysis results show fair agreement with the measurements of the pseudo-dynamic tests, and indicate that the modeling assumptions and the model parameters are reasonable. The ultimate horizontal force capacity predicted by the static non-linear analysis is 6670kN, 4.55 times the maximum base shear force under the earthquake excitation with peak acceleration of 3g. It is concluded that the PCCV for CNP1000 has sufficient aseismic safety.

关 键 词：预应力混凝土安全壳 1:10模型结构 拟动力试验 非线性分析 抗震安全 

分 类 号：TL364[核科学技术—核技术及应用]