绕丝交混模型对钠冷快堆组件子通道分析的影响  

Influence of wire wrap mixing model on sub-channel analysis ofsodium-cooled fast reactor assembly

作　　者：方闻韬 佟立丽[1] 曹学武[1] Fang Wentao;Tong Lili;Cao Xuewu(School of Mechanical Engineering,Shanghai Jiao Tong University,Shanghai 200240,China)

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《强激光与粒子束》2023年第9期123-128,共6页High Power Laser and Particle Beams

基　　金：国家自然科学基金项目(U1967202)。

摘　　要：钠冷快堆燃料棒表面缠绕的绕丝能够强化通道间的冷却剂横向流动,降低组件盒内温度分布的不均匀性,提升反应堆安全性。现有的子通道程序通过采用不同类型的绕丝交混模型,模拟了绕丝对组件盒内各类参数计算结果的影响。为了研究不同绕丝交混模型对钠冷快堆组件盒内流动与传热模拟的影响,基于Mikityuk对流传热模型以及Cheng-Todreas流动压降模型,分别采用强迫横流模型以及带绕丝湍流交混模型建立了子通道分析方法,并与美国ORNL开展的FFM-2A实验数据以及其他子通道程序针对该实验的分析结果进行了对比验证。结果表明在低流量条件下两种模型均能较好模拟带绕丝组件的流动与传热情况;在高流量条件下使用强迫横流模型分析结果与实验符合较好,使用带绕丝湍流交混模型的分析结果高估了靠近中心通道的出口冷却剂温度。The wire wrap on the surface of the fuel rods of the sodium cooled fast reactor can strengthen thetransverse flow of the coolant between the channels,reduce the unevenness of the temperature distribution in theassembly box,and improve the safety of the reactor.Different types of wire-wrap mixing models are used in sub-channel codes to simulate the effect of wire wrap on simulation results in an assembly.To study the influence ofdifferent wire-wrap mixing model on the simulation result of flow and heat transfer,based on the Mikityuk convectiveheat transfer model and the Cheng-Todreas flow pressure drop model,sub-channel analysis method has beenestablished with the forced cross flow model and the wire-wrapped turbulent mixing model respectively.The resultsare compared with the data of FFM-2A experiment carried out by ORNL and results of other sub-channel codes.It isfound that in the case of low flow rate,the two methods’simulation result fits the flow and heat transfer of the wire-wrapped assembly well.And in the case of high flow rate,the method of the forced cross flow model is consistent withthe experimental results,while the method of the wire wrapped turbulent mixing model overestimates the temperatureat the outlet of channel center.

关 键 词：钠冷快堆 绕丝组件盒 绕丝交混模型 子通道分析 反应堆热工水力 

分 类 号：TL364[核科学技术—核技术及应用]