基于流固耦合方法的300MWe级反应堆主泵叶片应力分析

Blade Stress of the Reactor Coolant Pump of 300 MWe Nuclear Power Plant in China Based on Fluid-solid Coupling Method

以国内某300MWe级核电站冷却剂泵为对象,从安全性出发,利用流固耦合技术,通过求解流体和固体耦合方程,对稳定工况下的叶片应力进行计算和分析。理论分析表明,主泵动静叶片的应力主要包括离心力引起的拉应力、流场压力引起的弯、扭应力和温度场产生的热应力;通过对计算结果进行分析,得到结论:最大米塞斯等效应力发生在固支约束处,叶片应力不具有严格的周期性,导叶体段复杂的内部流场是其应力分布无规律性的内在原因;综合对比计算和理论分析结果,证明动静叶片应力的差异性,并简要分析上述差异的主要影响因素。由第四强度理论进行的校核结果证明:主泵满足美国机械工程师协会(American Society of Mechanical Engineers,ASME)的强度要求。为改进叶片翼型设计、保障主泵水力性能和强度要求提供有效依据。

In order to compute and analyze the blade stress in reactor coolant pump of a 300 MWe nuclear power plant in China,from the viewpoint of safety performance,the fluid-solid coupling technique is adopted to solve the fluid and solid coupling equation.Theoretical analysis shows that the blade stresses mainly include tensile stress caused by centrifugal force,bending and torsional stresses induced by flow-field pressure,and thermal stress brought by temperature field.From the analysis results,it is concluded that the max equivalent（Von-Mises） stress exists in fixed supports and the blade stress does not have strict periodicity,and the disordered distributions of blade stress lies in the complex internal flow.The differences between impeller and guide vane are proved by comparison of theory and simulation and the main factors are explained.Lastly the intensity examination proves that the intensity of the reactor coolant pump meets the requirement of ASME.This could be used for improving aerofoil design and ensuring performance and intensity.