穿透概率法求解二维六角形几何多群中子积分输运方程  

Numerical Solution of Multigroup Integral Neutron Transport Equation for Hexagonal Geometry

作　　者：张颖[1] 谢仲生[1] 陈达[2] 江新标[2] 

机构地区：[1]西安交通大学,西安710049 [2]西北核技术研究所

出　　处：《西安交通大学学报》2000年第3期40-44,65,共6页Journal of Xi'an Jiaotong University

摘　　要：讨论了用穿透概率法求解二维六角形几何轻水堆燃料组件中子通量的分布 .提出了一种简易计算模型 .子区内中子源采用各向同性平源分布 ,子区表面通量在方向上采用简化 6P1近似 .根据提出的模型 ,编制了TPHEX A程序 ,并对一些轻水堆六角形组件问题作了计算 ,计算结果与DRAGON程序计算结果以及MC结果进行了比较 ,符合较好 .The flux distribution of two dimensional hexagonal geometry fuel assembly for LWR is studied,using the transmission probability method. The source within the mesh is assumed to be spatially uniform and isotropic. At the mesh surface, the constant and the simplified 6P 1 approximation are invoked for the anisotopic angular distribution. Based on proposed model,the code TPHEX A is implemented. Tested are some hexagonal LWR assembly problems. The calculated results are compared with those obtained from the MC method and DRAGON code. They are all in good agreement.

关 键 词：穿透概率 六角形 燃料组件 轻水堆 中子输运方程 

分 类 号：TL421.075[核科学技术—核技术及应用]