以AP1000为研究对象,针对非能动安全壳冷却系统(PCCS)结构系统的地震响应,包括屏蔽厂房的结构运动和重力水箱部分的刚体运动、对流运动和冲击运动等特点,基于顶部水箱及其屏蔽厂房的地震响应特点,分别建立隔震结构和普通结构的分析模型。根据核电厂结构特点和抗震规范要求,提出隔震参数优化分析模型,并基于MATLAB工作平台,实现隔震层周期和阻尼比的参数优化。通过优化隔震结构与普通结构、现行抗震规范隔震模型的比较表明,本文优化方法的隔震结构具有减震效果好、抗震性能稳定等优点。
PCCS in AP1000 includes two parts, namely a reinforced concrete containment, which is modeled as structural dynamic, and a gravity drain water tank, which is modeled as lumped masses known as sloshing mass, impulsive mass and rigid mass. Based on the seismic response characteristics of the water storage tank and the reinforced concrete containment, the conventional model and isolated model are built respectively. The optimal analysis of isolated layer parameters, namely the natural period and damping, are provided. Using the nuclear power plant dynamic characteristics and structural design codes, three models, namely conventional structure, isolated model on design code, and isolated model on the optimal parameter, are studied in MATLAB software. The seismic responses of all models are compared under the real earthquake ground motions. Results show that the isolated model with the optimal parameter provided by this paper has the best seismic function in all models.