摘要
为保障核承压热交换器的安全运行,采用数值模拟以及软件计算相结合的方法,对核承压热交换器两相流流致振动现象及减振措施进行了探究。研究结果表明:基于流致振动发生机理,热交换器横流速度、固有频率、卡门旋涡脱落频率以及紊流抖振频率为重点分析因素;由公式得出流量、换热管直径、换热管壁厚、管束排列等对流致振动有直接影响,无支撑跨距是影响管束流致振动较大因素;最易发生流致振动的部位包括入口区域、出口区域、折流板缺口区域以及无支撑跨距大管束;设计中,应在流量、换热管直径、壁厚、无支撑跨距、管束排列及入口防冲挡板设置等方面优化,以减小流致振动危害。
In order to ensure the safety of nuclear pressure retaining heat exchanger, the analysis for two phases flow flow-induced vibration of nuclear pressure retaining heat exchanger and control measures was presented by using computational fluid dynamics （CFD） and software calculation method. The results show that based on the theory of flow-induced vibration, crossflow velocity, natural frequency, vortex shedding frequency and turbulent buffeting frequency should be the key factors. Based on the formula,flow rate, tube diameter, tube wall thickness and pipe bundles layout have direct effects on flow-induced vibration, Unsupported tube span is the biggest factor influence flow-induced vibration. The most serious area of flow-induced vibration exists in inlet area, outlet area, baffle cut area and large unsupported tube span area. In the design, flow rate, tube diameter, tube wall thickness, unsupported tube span, pipe bundles layout and impingement baffle should be optimized, to reduce risk of flow-induced vibration.
出处
《核科学与工程》
CSCD
北大核心
2017年第5期727-734,共8页
Nuclear Science and Engineering
关键词
核承压热交换器
管束
两相流
流致振动
Nuclear pressure retaining heat exchanger
Pipe bundles
Two phases flow
Flow-induced vibration
