摘要
为了提高核电安全壳固有的安全性,设计了一种使用分离式热管的核电站安全壳非能动冷却系统。采用计算流体力学方法对安全壳小比例模型进行了三维数值模拟,得出了含有分离式热管非能动冷却系统的安全壳内的温度场和流场分布特性。结果表明:含分离式热管非能动冷却系统的安全壳内可形成以安全壳底部为热源、分离式热管蒸发段为冷源的自然对流循环;安全壳内高热源上方空间内的速度梯度相对于低热源附近的较大,这是由流体浮升力大小不同所导致的;安全壳内的蒸发段中,换热管热流密度随排数由外向内逐渐增大,各排蒸发管间的对流换热能力相差最大为7%。
In order to improve the inherent safety of nuclear power containment shell,a separate heat pipes-supported passive cooling system for the nuclear power plant containment shell was designed.Through having CFD method used to numerically simulate the small-scale model of the containment shell,the distribution characteristics of the temperature and the flow in the containment shell which containing the passive heat-pipe cooling system were obtained.The results show that,a natural convection cycle can be formed within the containment where the containment bottom is taken as the heat source and the evaporation section of the separated heat pipe as the cold source;the velocity gradient within the space above the high heat source in the containment shell is relatively larger than that near the low heat source,which is caused by the different buoyancy forces of the fluid;for the evaporation section in the containment shell,the heat flow rate of the heat transfer pipe increases gradually from the outside to the inside as the number of rows increases,and the difference of convection heat transfer capacity among evaporation pipes is less than 7%.
作者
孙海彤
虞斌
涂善东
SUN Hai-tong;YU Bin;TU Shan-dong(School of Mechanical Engineering, Nanjing University of Technology;School of Mechanical and Power Engineering,East China University of Science and Technology)
出处
《化工机械》
CAS
2018年第6期747-751,共5页
Chemical Engineering & Machinery
关键词
分离式热管
核电安全壳
非能动冷却
自然对流
温度场
流场
流体浮升力
separated heat pipe
nuclear power containment shell
passive cooling
natural convection
temperature field
flow field
fluid lift
