CAP1000反应堆堆内构件在直接安注下流动传热特性研究  

Investigation of Flow and Heat Transfer for CAP1000 Reactor Internals with Direct Safety Injection

作　　者：翁羽[1] 王海军[1] 王海涛[2] 张明[3] 冯少东[3] 顾红芳[1] Weng Yu;Wang Haijun;Wang Haitao;Zhang Ming;Feng Shaodong;Gu Hongfang(State Key Laboratory of Multiphase Flow in Power Engineering,Xi＇an Jiaotong University,Xi＇an,710049,China;Collaborative Innovation Center of High-End Manufacturing Equipment,Xi＇an Jiaotong University,Xi＇an,710049,China;Shanghai Nuclear Engineering Research and Design Institute,Shanghai,200233,China)

机构地区：[1]西安交通大学动力工程多相流国家重点实验室,西安710049 [2]西安交通大学高端制造装备协同创新中心,西安710049 [3]上海核工程研究设计院,上海200233

出　　处：《核动力工程》2018年第4期16-21,共6页Nuclear Power Engineering

摘　　要：在CAP1000反应堆中,使用了压力容器直接安全注射方式。由于安全注射管嘴和堆内构件的布置方式可能导致堆内构件承受较强的低温水影响,本文研究了吊篮外壁上布置的关键部件的表面温度分布及对流换热能力。使用缩比模型实验测量了堆内构件关键部位在不同安全注射条件下的壁面温度分布和换热系数,使用数值分析获得了堆内构件表面整体温度分布和换热系数。研究得到了辐照监督管顶部等危险区域上几个关键点的壁面温度和换热系数与安全注射条件间的无量纲关联式。For CAP1000 reactor, the coolant is injected in the reactor vessel under the accident condition through the method of direct injection. Because of the arrangement of the injection nozzle and the internals, the low temperature water has great effect on the reactor internals. The surface heat transfer capability of the reactor internals are studied in this paper. The surface temperature and heat transfer coefficient of the neutron shielding panels and the radiation surveillance capsules are investigated by scaled experiment and the numerical method under different injection conditions. The study found the dimensionless correlation between the wall surface temperature（and the heat transfer coefficient） and the injection flow rate conditions at several key points in the dangerous areas such as the top of the neutron shielding panel.

关 键 词：直接安注 堆内构件 换热 

分 类 号：TL334[核科学技术—核技术及应用]