SCDAP/Relap5 3.2程序分层夹带模型敏感性分析  

Sensitivity Analysis of Stratification Entrainment Model of SCDAP/Relap5 3.2 Code

作　　者：何双骥[1] 解衡[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《原子能科学技术》2012年第B09期320-323,共4页Atomic Energy Science and Technology

摘　　要：在AP1000中,连接堆芯补水箱和冷腿间的压力平衡管线中的气泡份额决定了堆芯补水箱的注入量,其中,气泡源自冷腿中的分层夹带。为研究AP1000核电站中气-液分层夹带现象对堆芯非能动余热排出系统的整体特性的影响,本文以Relap5/Mod3.2作为计算平台,建立了AP1000小破口失水事故模型并进行了数值计算,对比了采用与不采用水平分层夹带模型的计算结果,发现该模型对事故发展有重要的影响。The void fraction on the pressure-balance-line（PBL）,which connecting core makes tank（CMT） and cold leg in AP1000,determines the injection of CMT.The steam in the PBL comes from the entrainment of cold leg.To study the effect of horizontal stratification entrainment on the characteristics of AP1000 passive core cooling system,a numerical modeling of AP1000 using the best estimate code Relap5/Mod3.2 was developed.The small break loss of accident（SBLOCA） was simulated.Comparisons of the results with and without entrainment model show that existing horizontal stratification entrainment model of Relap5 is very sensitive and important to the short-term of LOCA,and has significant impact on the entire SBLOCA process.

关 键 词：AP1000 数值分析 小破口事故 水平分层夹带 

分 类 号：TL333[核科学技术—核技术及应用]