论文部分内容阅读
本文讨论二维轻水堆燃料组件内中子通量和功率分布的计算。文章第一部分讨论穿透几率方法,提出了一种简易的计算模型。在子区内,中子通量采用线性分布,子区表面上采用P_1近似角分布和线性空间分布,对展开系数导出了简便的表达式,即用表面上的出射和入射中子流来决定,并在迭代过程中逐步更新和精确化,因而减少了求解的未知量,简化了计算。文章第二部分讨论块方法的应用以及栅元等效圆柱化的误差。根据提出的模型,编制了二维TPM2D和BTM计算程序。对轻水堆的一些组件基准问题作了计算。计算结果与其它方法进行了比较,其结果符合得很好。本程序可用于轻水堆燃料组件的计算。
This article discusses the calculation of neutron flux and power distribution in a two-dimensional light-water reactor fuel assembly. The first part of the article discusses penetration probability method and presents a simple calculation model. In the subregion, the neutron flux is linearly distributed, and the P 1 approximate angular distribution and the linear spatial distribution on the surface of the subregion are used to derive a simple expression for the expansion coefficient, that is, the exit and incident neutron flux on the surface , And gradually updated and refined during the iteration process, thus reducing the unknown quantity of the solution and simplifying the calculation. The second part of the article discusses the application of the block method and the error of the equivalent cylindrical cell. According to the proposed model, a two-dimensional TPM2D and BTM calculation program has been developed. Some components of the light water reactor benchmark problem has been calculated. The calculated results are compared with other methods and the results are in good agreement. This procedure can be used for the calculation of light water reactor fuel assemblies.