一种求解反应堆中子扩散方程和输运方程的方法

A Method for Solving Reactor Neutron Diffusion Equation and Transport Equation

  • 摘要: 结合反应堆中子物理方程的特点和非结构网格技术,提出了一种在任意网格下求解反应堆中子物理方程的方法。以反应堆中子扩散方程和一阶离散纵标的输运方程为例,从空间离散、方程离散和边界条件实施等方面介绍了该方法的实施过程。利用该方法编制的程序计算了BN-600基准题、CFR1000概念堆和BWR栅元3种情况的有效增殖因数,并与其他程序的计算结果进行了对比,初步验证了该方法的合理性。

     

    Abstract: Combining the feature of reactor neutron physics equation and non-structure mesh technology, a method appropriating for structure/non-structure mesh calculation was proposed. Taking the reactor neutron diffusion equation and 1st order discrete ordinate transport equation as an example, the implementation of the method was introduced by demonstrating the region discretization, the equation discretization and the implementation of boundary condition. The code developed using the method calculated the effective multiplication factors of BN-600, CFR1000 and BWR cell. The comparison of calculation results between the code and other codes shows that the method for reactor physics analysis is reasonable.

     

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