棒束通道内混合对流传热实验研究  

Experimental Study on Mixed Convection Heat Transfer in Rod Bundles

作　　者：刘达[1] 顾汉洋[1] Liu Da;Gu Hanyang(School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai, 200240, Chin)

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《核动力工程》2018年第3期13-17,共5页Nuclear Power Engineering

摘　　要：以自然循环下堆芯内可能会发生的低流量传热为研究背景,对5×5棒束通道内的混合对流传热现象进行了实验研究。实验压力为6 MPa,质量流量为25~150 kg/(m^2·s),热流密度为25~300 kW/m^2,实验雷诺数Re为1000~30000,浮升力参数Bo*为2×10^(-7)~3×10^(-3)。实验发现,随着Bo*的增大,棒束通道内传热产生先弱化后强化的趋势。浮升力对棒束通道内传热造成影响的起始点为Bo*=3.5×10^(-6),当Re>15000时,浮升力依然可对传热造成弱化现象。基于实验数据,提出了适用于棒束通道的混合对流经验关系式。With the background of the low flow rate heat transfer in case of the natural circulation in the reactor, the mixed convection was experimentally studied in a 5×5 rod bundles. The experiment was performed at 6 MPa, the mass flow rate from 25 to 150 kg/（m^2·s）, the heat flux from 25 to 300 kW/m^2, Reynolds number from 1000 to 30000, Buoyancy parameter from 2×10^-7 to 3×10^-3. It is concluded that with the increasing of the Buoyancy parameter, the heat transfer in rod bundles was impaired firstly and then followed by enhancement. It is observed that in the rod bundle channel, the influence of the buoyancy force occurs at Bo＊=3.5×10^-6. Even when Reynolds number is higher than 15000, the heat transfer could be impaired by the buoyancy force. An empirical correlation used to calculate mixed convection heat transfer in rod bundles was proposed based on the experimental data.

关 键 词：混合对流 棒束 浮升力 传热 

分 类 号：TK124[动力工程及工程热物理—工程热物理]