研究利用穿透概率法求解二维六角形轻水堆燃料组件内中子通量密度分布。
The paper describes the model for calculating the neutron flux density distribution in two dimensional hexagonal geometry assembly of light water reactor (LWR) by transmission probability method.
六角形节块内的中子通量密度分布采用高次多项式近似表示，最后导出通量矩方程及偏流的响应矩阵方程。应用粗网再平衡和渐近源外推方法加速收敛。
The nodal equations and response matrix equations are derived using higher order polynomial approximations to the spatial dependence of the flux within the hexagonal-z node.
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