摘要
本文以水-水换热整圆形孔板纵流型管壳式换热器为背景,对核级换热设备在流致振动方面的设计校核过程进行了详细介绍。文中介绍了管束流致振动机理,分析了该换热器在这方面较为薄弱的环节,提供了相应的校核判据、计算方法、过程及设计考虑,探讨与分析了99版TE-MA较88版TEMA及99版GB151在流致振动判据上的改进之处,可为该类型换热器在核电站中的设计与应用作参考。
Based on the longitudinal-flow heat exchanger of shell-and-tube type with circle orifice baffle,the check process of the designed water-to-water heat exchanger with nuclear class is specified,regarding the flow induced vibration.The mechanism of flow induced vibration is introduced,in terms of which the weak positions of the researched heat exchanger are analyzed.Then,the relevant check criteria,calculation method and process and the design considerations are presented.Furthermore,the improvement of the 8th edition of TEMA compared to the 7th edition of TEMA and GB151-1999 in the aspect of flow induced vibration is discussed and analyzed.These conclusions can be taken as a reference for the design and application of this type heat exchanger in the nuclear power plant.
出处
《节能技术》
CAS
2012年第4期370-373,共4页
Energy Conservation Technology
关键词
换热器
核电站
流致振动
heat exchanger
nuclear power plant
flow induced vibration
