向量裂变谱与矩阵裂变谱对临界计算的影响  

THE EFFECT OF VECTOR FISSION SPECTRUM AND MATRIX FISSION SPECTRUM ON THE CRITICAL CALCULATION

作　　者：邓力[1] 刘瑞兰[2] 谢仲生[2] 

机构地区：[1]北京应用物理与计算数学研究所,北京100088 [2]西安交通大学能动学院核能工程系,陕西西安710049

出　　处：《计算物理》2002年第1期67-72,共6页Chinese Journal of Computational Physics

基　　金：中国工程物理研究院 ( 2 0 0 10 6 6 0 )

摘　　要：用蒙特卡罗方法及可适应多种截面的三维多群P3 中子输运蒙特卡罗程序MCMG ,计算比较了不同裂变材料使用向量裂变谱与矩阵裂变谱的计算结果 ,通过与MCNP程序结果的比较 ,确信两种裂变谱对计算结果的影响是存在的 ,但对计算结果不会带来本质影响 .When the fission reaction happens in neutron transport calculation,the energy of the fission neutron can be usually determined by the fission spectrum.Since the coefficient of the spectrum type depends on the incident neutron energy,the multigroup neutron fission spectrum should strictly be a matrix form.In general transport calculation,the 235 U vector fission spectrum is usually chosen as the standard fission spectrum.In order to make clear what kind of effect will be produced after this treatment,the Monte Carlo method and the multigroup P 3 Monte Carlo neutron transport code MCMG are used to analyze the difference between two types of fission spectrums.By comparison the results with MCNP code,it is certain that the difference exists,but it does not have any effect on the correction of the calculated results.At the same time,the calculation results of the different neutron cross section libraries have been compared. [

关 键 词：矩阵裂变谱 向量裂变谱 临界计算 蒙特卡罗法 中子 

分 类 号：O571.5[理学—粒子物理与原子核物理]