摘要
利用自主开发的确定论数值反应堆物理计算程序NECP-X对VERA(virtual environment for reactor application)9#基准题进行全堆芯精细建模计算,显式描述了堆芯格架、管座、端塞、压紧弹簧及气腔等结构,计算得到了整个寿期中的临界硼质量分数,给出了3维全堆芯棒功率分布、燃料有效温度分布及慢化剂温度分布,并将计算结果与实测值进行了比较。结果表明,整个寿期中临界硼质量分数的计算值与实测值的偏差小于2.5×10^(-5),计算精度较好;在整个寿期内,随着燃耗的加深,堆芯功率分布逐渐展平,燃料有效温度及慢化剂温度的分布逐渐变得均匀,符合物理规律及预期。
In this paper,NECP-X,a self-developed deterministic numerical reactor code,is used to model and calculate the whole core of the virtual environment for reactor application(VERA)benchmark problem 9^(#).Detailed axial reflector regions,including plenum,end plugs,end gaps,nozzles,and core plates are simulated explicitly.The critical boron concentration in the entire lifetime is calculated.At the meantime,some fine parameters such as three-dimensional normalized pin power distribution,the effective fuel temperature distribution,and the moderator temperature distribution are given,and the calculated results are compared with the measured values.The calculation results show that the deviation of the critical boron concentration is less than 2.5×10^(-5) compared with measured value and the code is in high precision.During the entire lifetime,with the burnup increases,the core power distribution gradually flattens,the fuel effective temperature and the moderator temperature distribution gradually become uniform,which conforms to the laws of physics and expectations.
作者
张旻婉
刘宙宇
温兴坚
吉文浩
ZHANG Min-wan;LIU Zhou-yu;WEN Xing-jian;JI Wen-hao(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;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83-88,共6页
Modern Applied Physics
基金
国家科技重大专项经费资助项目(2019ZX06002033)。
