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对于压水堆燃料组件而言,栅格稠密、几何形状复杂,对中子的吸收较强。在这种情况下,如果采用扩散理论计算这种组件内的中子分布,会引起相当大的误差,但蒙特卡罗方法是非常适合于处理这种情况的。按照本文所提出的物理模型,只要计算的中子数足够多,其计算结果可完全在实验误差范围之内。本文提出的物理模型的准确度,已为国内外大量物理实验所证实,并已用于国内压水堆物理设计。 本文在处理热能区的散射碰撞时,考虑了各向异性散射及分子间化学键的影响;在处理高能区的散射碰撞时,还考虑了非弹性散射。
For PWR fuel assemblies, the grids are dense, complex in geometry, and strongly absorb neutrons. In this case, calculating the neutron distribution within such an assembly using diffusion theory can cause considerable errors, but the Monte Carlo method is well suited to deal with this situation. According to the physical model proposed in this paper, as long as the calculated number of neutrons enough, the calculation results can be completely within the experimental error range. The accuracy of the physical model proposed in this paper has been verified by a large number of physical experiments at home and abroad and has been used in the physical design of pressurized water reactors in China. In this paper, anisotropic scattering and intermolecular chemical bonds are considered when dealing with scattering collisions in the thermal energy region. In the treatment of scattering collisions in the high energy region, inelastic scattering is also considered.