摘要
设计了ZH-65型蒸汽发生器传热管束的试验模型,在空气-水两相流回路上对ZH-65型蒸汽发生器传热管束迚行流致振动研究。测量了U形管在空泡仹额为0%~90%、缝隙流速为0.5~3.43 m/s时的应变和加速度响应。从弯曲半径的大小、面内与面外、弯管段与直管段等方面对传热管束迚行评价。研究表明,弯曲半径越大,弯管段的加速度越大;弯管段根部应变与弯曲半径成反比;传热管的频率与弯曲半径成反比;弯管段的面内加速度比面外的小;弯管段的加速度比直管段的大。
An experimental model of heat transfer tube bundles of ZH-65 steam generator was designed.Then the flow-induced vibration of heat transfer tube bundles of ZH-65 steam generator was studied in air-water two-phase flow loop.The strain and acceleration responses of U-tube were measured under void fraction of 0%~90%and pitch velocity of 0.5~3.43 m/s.The evaluation of tube bundles was conducted from the size of bending radius,in-plane and out-of-plane,bending section and straight section,etc.The results show that the acceleration of bending section increases with the increase of the bending radius.The strain at the root of the bending section is inversely proportional to the bending radius.The frequency of U-tube is inversely proportional to the bending radius.The in-plane acceleration of the bending section is smaller than that of the out-of-plane acceleration.The acceleration of the bending section is greater than that of the straight section.
作者
谭添才
高李霞
李朋洲
杨杰
马建中
席志德
Tan Tiancai;Gao Lixia;Li Pengzhou;Yang Jie;Ma Jianzhong;Xi Zhide(Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第A01期63-66,共4页
Nuclear Power Engineering
关键词
U形管
两相流
流致振动
空泡仹额
U-tube
Two-phase flow
Flow-induced vibration
Void fraction