旋转型三维隔震体系试验研究及动力响应分析

Experimental study and dynamic response analysis of rotational three-dimensional seismic isolation system

为深入研究旋转型三维隔震体系的受力性能及隔震效果,建立了其考虑摩擦因素的竖向刚度计算方法,提出了包含初始承载力的竖向滞回模型,并给出了关键参数的计算式。对隔震支座模型进行了竖向压缩拟静力试验,在此基础上进行了力学参数相关性分析,得到摩擦系数与倾斜角度对竖向性能的影响规律。最后对使用该隔震体系的核反应堆厂房进行水平及竖向地震荷载作用下的动力响应分析,比较结构在基准地震、安全停堆地震、超设计基准地震下的地震响应,发现隔震层及上部各楼层加速度响应均有显著减小。进一步得到了厂房内部关键节点的加速度反应谱,发现该体系可将核反应堆厂房隔震结构设计地震动峰值加速度由0.3g提升至0.6g,可有效地增加核电厂选址范围。

In order to deeply study the mechanical properties and isolation effects of the rotational three-dimensional seismic isolation system, a vertical stiffness calculation method considering the friction factor was established. A vertical hysteretic model including the initial bearing capacity was proposed and the calculation formulae of the key parameters were given. The vertical quasi-static compression tests were carried out on the isolation bearing model, based on which the correlation analysis of mechanical parameters was carried out and the influence of friction coefficient and inclination angle on the vertical performance was obtained. Dynamic response analysis was conducted on a nuclear reactor building using the isolation system under horizontal and vertical loads, based on which the seismic responses of the structure under the baseline earthquake(OBE), the safe shutdown earthquake(SSE) and the overdesign reference earthquake were compared. The results show that the acceleration response of the isolation layer and the upper floors are significantly reduced. The acceleration response spectrum of key nodes inside the plant was further obtained, and it is found that the system can increase the design ground motion of the seismic isolation structure of nuclear reactor plant from 0.3g to 0.6g, which can effectively increase the site selection range of nuclear power plants.