低温堆上空腔破口失水后期的流动振荡实验研究  

Experimental Study for Flow Oscillation under SBLOCA on Upper Plenum of Nuclear Heating Reactor

作　　者：博金海[1] 姜胜耀[1] 张佑杰[1] 贾海军[1] 

机构地区：[1]清华大学核能技术设计研究院,北京102201

出　　处：《核动力工程》2000年第6期515-518,545,共5页Nuclear Power Engineering

基　　金：国家自然科学基金资助项目!(19872040)

摘　　要：在 5MW低温堆的模拟试验台架 HTRL- 5上对该低温堆上空腔破口失水事故进行了实验研究。重点研究了事故后期的流动振荡现象，揭示了振荡的发展过程和发生机理。经实验研究，给出了小破口失水闪蒸过程中回路内压力、温度、空泡份额、循环流量等重要参数的变化规律，同时表明了小破口失水过程中由于压力下降引起闪蒸产生大量气泡并引起自然循环流量的变化，这些变化又反过来对各参数产生影响，使循环流量和传热情况发生周期性变化。Experimental results of flow oscillation under small break loss- of- coolant accident(sbLOCA) on upper plenum of nuclear heating reactor are presented in this paper.The experiment is carried out on the thermohydraulic test system HRTL- 5 of the 5MW nuclear heating reactor,which is a natural circulation system.The variations of pressure,temperature,void fraction,and circulation mass flow are described.Flow oscillation is described and its development mechanism is studied specially.Results show that the pressure decreasing in LOCA and bubbles producing caused by flashing,and mass flow variation have influence on each other and cause cyclical variations of flow and heat transfer.

关 键 词：5MW低温堆 小破口失水事故 流动振荡实验 

分 类 号：TL364.4[核科学技术—核技术及应用]