摘要
对某溶液堆堆芯内呈纵向螺旋状盘绕的传热管束进行了流致振动试验研究,包括结构在空气中和静水中振动特性的计算和试验以及稳态和瞬态运行工况下的流致振动试验。试验结果表明,传热管束入、出口之间的压力差随流速的增加而增加,且上部固定连接端是相对薄弱的部位。在稳态运行时不会发生动力失稳,振动位移不会造成管束各管段之间发生接触碰撞,疲劳分析表明满足规范要求。瞬态响应最大振动位移和应变均比稳态运行时高两个数量级以上。
The flow induced vibration(FIV) tests of heat transfer helical tube bundle of a liquid-reactor were carried out.Two parts were included: Calculation and test on vibration characteristics in air and water of structure;FIV test in steady-state and transient condition.The results show that the larger internal flow velocity becomes,the higher pressure drop of bundle is,and the up restraint positions are weak.The dynamic buckling of bundle does not occur during steady-state operation,the tubes are not contacted,and the fatigue evaluation was done according to ASME code and the structure is founded to satisfy the ASME code requirements.The transient maximum vibration displacements and strains are larger 2 orders than steady-state values.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2008年第S2期468-471,共4页
Atomic Energy Science and Technology
关键词
溶液堆
螺旋式
传热管束
流致振动
liquid-reactor
helical
heat transfer tube bundle
flow induced vibration