熔盐冷却球床实验堆内流动与传热特性数值研究  

Numerical Studies on Flow and Heat Transfer Characteristics of Fluoride Salt Cooled Pebble Bed Test Reactor

作　　者：魏诗颖 王成龙[1,2] 田文喜 苏光辉[1,2] 秋穗正[1,2] Wei Shiying;Wang Chenglong;Tian Wenxi;Su Guanghui;Qiu Suizheng(School of Nuclear Science and Technology,Xi＇an Jiaotong University,Xi＇an,710049,China;State Key Laboratory of Multiphase Flow in Power Engineering,Xi＇an Jiaotong University,Xi＇an,710049,China)

机构地区：[1]西安交通大学核科学与技术系,西安710049 [2]西安交通大学动力工程多相流国家重点实验室,西安710049

出　　处：《核动力工程》2018年第4期1-5,共5页Nuclear Power Engineering

基　　金：国家自然科学基金资助项目(91325201;10575079)

摘　　要：采用计算流体动力学(CFD)的方法,对熔盐冷却球床堆(FHR)的堆芯中可能产生热点的位置进行局部数值模拟,从而获得燃料球表面及其内部的温度分布和燃料球附近的流场分布情况,并与所开发的FRAC分析程序结果进行对比,其最大误差为2.9%,可以初步说明FRAC程序的正确性。本文的研究结果对FHR相关实验以及机理的研究具有一定的参考价值。In this paper, the detailed local flow and heat transfer phenomena are investigated by computational fluid dynamics（CFD） for the locations that may have the maximum pebble temperature. The distributions of temperature on the surface or in the fuel pebble, and the velocity field near the fuel pebble are obtained and analyzed. Results are compared with that acquired by in-house code FRAC and the maximum relative error is 2.9%, which preliminarily proves the accuracy of FRAC. This study can provide useful information to the experimental and mechanism research of FHR.

关 键 词：熔盐冷却球床堆(FHR) 热工-水力 计算流体动力学(CFD) 

分 类 号：TL333[核科学技术—核技术及应用]