摘要
基于3维时空中子动力学计算软件CORCA-K、堆芯热工水力计算软件CORTH及截面更新计算软件PACFAC,研制了压水堆堆芯多专业耦合计算软件COMPCS。采用压水堆弹棒基准题NEACRP和MOX/UO 2对COMPCS软件的弹棒事故模拟能力进行了验证,并对“华龙一号”堆芯首循环弹棒事故开展了模拟计算,分析了初始功率水平和弹棒时间对弹棒过程中堆芯相对功率、燃料芯块温度峰值和包壳温度峰值的影响。结果表明,COMPCS软件对2种基准题的计算结果与相应的参考结果符合良好,具有较高的计算精度;在寿期末,初始功率水平较高、且弹棒时间较短时,堆芯相对功率水平上升速率更快,会形成功率和燃料温度峰值;在首循环典型弹棒过程中,“华龙一号”燃料芯块温度峰值和包壳温度峰值均低于设计限值,不会威胁包壳的完整性。
Based on three dimensional space-time neutron dynamics calculation software CORCA-K,the core thermal hydraulic calculation software CORTH,and the section-updating calculation software PACFAC,a multi-physical coupling calculation software COMPCS for the core of typical pressurized water reactor(PWR)is developed.Benchmark NEACRP and MOX/UO 2 are used to verify the simulation capability of COMPCS software to the rod ejection accident.The rod ejection accident simulation is carried out for the first cycle of HPR1000 core,and the influence of different initial power level and rod ejection time on the relative core power,the fuel peak temperature,and the cladding peak temperature during rod ejection process are studied.The two benchmark results calculated by using COMPCS software are in good agreement with the reference results and the calculation accuracy is high.At the end of life,when the initial power level is higher and the rod ejection time is shorter,the core relative power increases faster,the peak power and the fuel peak temperature will be formed.In the typical rod ejection process of the first cycle,fuel peak temperature and cladding peak temperature of HPR1000 are lower than the designed limit value,which will not threaten the integrity of the cladding.
作者
李治刚
安萍
潘俊杰
赵文博
刘卢果
宫兆虎
芦韡
强胜龙
贺涛
LI Zhi-gang;AN Ping;PAN Jun-jie;ZHAO Wen-bo;LIU Lu-guo;GONG Zhao-hu;LU Wei;QIANG Sheng-long;HE Tao(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《现代应用物理》
2021年第1期26-34,共9页
Modern Applied Physics
