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首页> 外文会议>International conference on the physics of reactors;PHYSOR 2010 >ANALYTIC BASIS FUNCTION EXPANSION METHOD FOR NEUTRON DIFFUSION CALCULATION IN THE ARBITRARY TRIANGULAR NODES
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ANALYTIC BASIS FUNCTION EXPANSION METHOD FOR NEUTRON DIFFUSION CALCULATION IN THE ARBITRARY TRIANGULAR NODES

机译：任意三角形节点中子扩散计算的解析基函数展开法

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A new nodal method for directly solving the neutron diffusion equation in the arbitrary triangular nodes was proposed. The neutron flux distributions within a node were expanded in a series of analytic basis functions for each group. Nodes were coupled each other with both the zero- and first-order partial neutron current moments simultaneously. The relationships between a regular triangle and an arbitrary triangle are utilized to describe the neutron current moments. With a new sweeping scheme developed for arbitrary triangular node, the response matrix technique was used to solve the nodal diffusion equations iteratively. Based on the proposed model, the code ABFEM-T was developed. The numerical results for a series of benchmark problems show that the core multiplication factor and nodal powers are predicted accurately using this model for unstructured neutron diffusion problems.
机译：提出了一种直接求解任意三角节点中子扩散方程的节点方法。对于每个组，节点内的中子通量分布以一系列解析基础函数进行了扩展。节点同时以零阶和一阶部分中子电流矩彼此耦合。正三角形和任意三角形之间的关系用于描述中子电流矩。通过为任意三角形节点开发新的扫描方案，使用响应矩阵技术迭代求解节点扩散方程。基于提出的模型，开发了代码ABFEM-T。一系列基准问题的数值结果表明，使用该模型对非结构化中子扩散问题可以准确地预测堆芯倍增系数和节点功率。

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