| 穿透概率法求解二维六角形几何多群中子积分输运方程 |
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| 引用本文： | 张颖,谢仲生,陈达,江新标. 穿透概率法求解二维六角形几何多群中子积分输运方程[J]. 西安交通大学学报, 2000, 34(3): 40-44,65 |
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| 作者姓名： | 张颖 谢仲生 陈达 江新标 |
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| 作者单位： | 1. 西安交通大学,710049,西安
2. 西北核技术研究所 |
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| 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，本程序可用于轻水堆六角形燃料组件计算。
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| 关 键 词： | 穿透概率 六角形 燃料组件 轻水堆 中子输运方程 |
| 文章编号： | 0253-987X（2000）03-0040-05 |
Numerical Solution of Multigroup Integral Neutron Transport Equation for Hexagonal Geometry |
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| Zhang Ying,Xie Zhongsheng,Chen Da,Jiang Xinbiao. Numerical Solution of Multigroup Integral Neutron Transport Equation for Hexagonal Geometry[J]. Journal of Xi'an Jiaotong University, 2000, 34(3): 40-44,65 |
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| Authors: | Zhang Ying Xie Zhongsheng Chen Da Jiang Xinbiao |
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| Abstract: | 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. |
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| Keywords: | transmission probability hexagonal geometry fuel assembly neutron flux |
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