压水堆稳压器波动管热分层现象流固耦合传热数值模拟_刘彤.pdf

第33 卷 第2 期 中 国 电 机 工 程 学 报 Vol.33 No.2 Jan.15, 2013 2013 年1 月15 日 Proceedings of the CSEE ©2013 Chin.Soc.for Elec.Eng. 79 文章编号：0258-8013 (2013) 02-0079-07 中图分类号：TK 122 文献标志码：A 学科分类号：470·20 压水堆稳压器波动管热分层现象的流固耦合传热 数值模拟 刘彤，王雪彩，衣书宾 ( 电站设备状态监测与控制教育部重点实验室(华北电力大学) ，北京市 昌平区 102206) Fluid-solid Conjugate Heat Transfer Numerical Simulation of Pressurized Water Reactor Pressurizer Surge Line Subjected to Thermal Stratification LIU Tong, WANG Xuecai, YI Shubin (Key Laboratory of Condition Monitoring and Control for Power Plant Equipment, Ministry of Education (North China Electric Power University), Changping District, Beijng 102206, China) ABSTRACT: 3-D full-scale transient computational fluid 0 引言 dynamics (CFD) technique involving fluid-solid conjugate heat 水平管道中滞止或缓慢流动着具有较大温差 transfer (CHT) was employed for investigating flow and heat (密度差) 的冷、热2 种流体时，较冷流体密度大， transfer in pressurized water reactor (PWR) pressurizer surge 积聚在水平管道的下部；较热流体密度小，占据管 line subjected to thermal stratification. Compared to past models, computing control domain was extended to solid wall 道的上部空间即所谓的热分层现象。目前，压水堆 region of surge line and shear stress transport (SST) K-ω (pressurized water reactor，PWR)核电站的一回路冷 turbulent model was adopted for more suiting to secondary 却系统主要以水为冷却介质。由于水的导热系数较 flow and fluid separation. More efficient method of calculation 小而比热容却很大，这个特性使得水平管道系统 was utilized for evaluating effects of buoy