核电站反应堆冷却剂泵的模态分析

Mode Analysis of Reactor Coolant Pump for Nuclear Power Station

以某核电站反应堆冷却剂泵(以下简称核泵)为研究对象,对核泵结构进行适当简化后,建立有限元模型,并在有连杆和无连杆两种工况下,计算核泵的固有频率,得出了其前12阶固有频率和振型,并结合核泵具体结构对其固有频率和振型进行了简要说明,计算了阻尼器、拉杆和立柱刚度对核泵固有频率的影响。分析结果可以为下一步进行核泵的地震响应分析提供理论依据。

With the reactor coolant pump （nuclear pump for short hereinafter） in a nuclear power station taken as the subject for research, a model of finite element is set up after the structure of the nuclear pump has been reasonably simplified. The natural frequencies of the pump with and without connecting rod are calculated so that the natural frequencies and mode shapes of its first 12 steps are obtained. Based on the specific structure of the nuclear pump, the natural frequency and mode shape are explained briefly. The influence of snubber, tie rod and column on the natural frequency of the nuclear pump is computed. The analytic results can be used as the theoretical base for further earthquake response analysis of the nuclear pump.