安注过程蒸汽直接接触冷凝的数值模拟  

Numerical simulation of steam direct contact condensation during safe injection

作　　者：王高宇 陈伟[2] 申亚欧[2] 卢涛[1] WANG GaoYu;CHEN Wei;SHEN YaOu;LU Tao(College of Mechanical and Electrical Engineering,Beijing University of Chemical Technology,Beijing 100029;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]北京化工大学机电工程学院,北京100029 [2]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《北京化工大学学报（自然科学版）》2021年第6期79-86,共8页Journal of Beijing University of Chemical Technology(Natural Science Edition)

基　　金：国家自然科学基金(51776014)。

摘　　要：压水反应堆发生失水事故(LOCA)时,应急堆芯冷却系统(ECCS)将过冷的安注水注入到冷管段中,安注水与管道中的蒸汽发生直接接触冷凝,导致温度波动及压力振荡。选用流体体积分数模型、大涡湍流模型和双阻力冷凝模型,在FLUENT平台上对饱和蒸汽与安注水直接接触冷凝过程进行数值模拟,获得直接接触冷凝过程中温度场和压力场的变化情况。结果表明,冷凝主要发生在汽液界面附近,主管内蒸汽流量的增加能够阻止安注水回流现象发生。During a loss of coolant accident in a pressurized water reactor(PWR),direct contact condensation oc-curs when the water undergoing safe injection from the emergency core cooling system pipe is poured into the cold leg,resulting in temperature fluctuations and pressure oscillations.The volume of fluid model,large eddy simula-tion and two resistance condensation model of FLUENT have been used to simulate the direct contact condensation process.By analyzing the mechanism of steam direct contact condensation,the variation characteristics of the tem-perature field and pressure field have been obtained.The numerical results indicate that the direct contact conden-sation mainly occurs at the two-phase interface,and increasing the steam mass flow in the main pipe can prevent the backflow of cooling water.

关 键 词：安注 失水事故(LOCA) 直接接触冷凝 数值模拟 

分 类 号：TL334[核科学技术—核技术及应用]