某核电厂管壳式换热器流致振动分析

Analysis on Flow Induced Vibration of Shell and Tube Heat Exchanger in a Nuclear Power Plant

为查找某核电厂疏水冷却器(管壳式换热器)换热管断裂的原因,本文采用ANSYS软件对换热管进行建模,确定管束的自振频率,利用TEMA标准计算换热管束的卡门漩涡脱落频率、临界流速及振幅。通过自振频率与卡门漩涡脱落频率对比及实际流速与横流流速的对比判定,确定了卡门漩涡脱落及流体弹性不稳定是导致疏水冷却器换热管束断裂的根本原因。提出针对性的解决措施,其成果对于核电站管壳式换热器的安全运行有借鉴意义。

In order to find the reasons of the tube bundle fracture in a nuclear power plant＇ s drain cooler （a shell and tube heat exchanger）, establishes a pipe model to determine the natural frequency of the tube bundle by ANSYS, and determines the vortex shedding frequency, the critical flow velocity and vi- bration amplitude according to TEMA standards. The study finds that the vortex shedding and fluid elastic instability are the root causes of the tube bundle fracture by comparing the natural frequency of vibration with the vortex shedding frequency and comparing the actual flow velocity with the critical flow velocity. A series of specific countermeasures is provided. The achievements obtained can provide safe operating of heat exchengers in nuclear power plants.