“华龙一号”安全壳热工水力现象综合性能实验数值计算研究  

Numerical simulation of the thermal hydraulic experiment of the integral test facility of HPR1000 containment(PANGU)

作　　者：李精精 王辉 孙婧 LI Jingjing;WANG Hui;SUN Jing(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China)

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《应用科技》2023年第5期110-114,共5页Applied Science and Technology

基　　金：国家重点研发计划项目(2020YFB1901401).

摘　　要：为了更好地研究事故条件下非能动安全壳热量导出系统作用下安全壳内的热工水力行为,中国核电工程有限公司搭建安全壳综合性能实验装置(PlAtform for iNteGral TH behaviour of containment,PANGU)并开展了3种事故序列大破口事故(堆芯未熔)、大破口事故(堆芯熔化)和全厂断电事故下的实验研究。采用GOTHIC程序建立安全壳综合性能实验装置数值计算模型,并针对已开展的3个实验进行数值计算研究,得出结论如下:对于3个事故序列,程序计算的穹顶区域水蒸气浓度与实验值趋势上保持一致,特别是长期阶段水蒸气浓度实验值与计算值符合良好;计算模型所计算的安全壳内温度压力无论是峰值还是长期值均与实验值保持在较小的误差范围内;简化后的PCS模型计算的PCS功率略低于实验测量的PCS功率,72 h内计算的PCS总排热量与实验测量值相当。本文研究结果可为“华龙一号”PCS系统计算分析提供理论支持。In order to better study the thermal hydraulic behavior in the containment under the action of passive containment heat removal system(PCS)when accident occurs,the integral test facility—PlAtform for iNteGral TH behaviour of containment(PANGU)established by China Nuclear Power Engineering Co.,Ltd.was used to carry out experimental research,including three kinds of accident scenarios:large LOss of Collant Accident—LOCA(core not melted),large LOCA(core melted)and the station blackout accident(SBO).The programme GOTHIC was used to establish the numerical model of PANGU,and carry out the numerical calculation for the above three scenarios of experiment.The conclusions are drawn as follows:for the three accident sequences,the water vapor concentration in the dome calculated by GOTHIC is consistent with experimental value in terms of tendency.Especially,in the long term stage,the vapor concentration is in good agreement with the experiment values.Both the peak and long term values of the temperature and pressure in the containment calculated by GOTHIC are kept within a small error range from the experimental values.The PCS power calculated by the simplified PCS model is slightly lower than the measured value in the experiment.Within 72 hours,the calculated total heat output of the PCS is equivalent to the measured value in the experiment.The results of this paper can provide theoretical support for the PCS calculation of HPR1000.

关 键 词：安全壳综合性能实验装置 非能动安全壳热量导出系统 GOTHIC程序 华龙一号 热工水力 严重事故 安全壳 数值模拟 

分 类 号：TL364.4[核科学技术—核技术及应用]