基于碰撞的混合方法计算多群中子输运
Multigroup Neutron Transport using a Collision-Based Hybrid Method
摘要：
将中子输运方程离散纵标近似的基于碰撞的混合算法推广到多群情形。该算法使用两种不同分辨率的离散能量和角度网格，并在粗网格上近似裂变和散射源。耦合的碰撞输运方程，离散的粗网格，与未碰撞的输运方程，离散的细网格，产生一个算法，在大多数情况下，比传统的多组方法更有效。对现有技术的改进证明了与时间相关的问题，不同的材料，几何形状，和能源集团。
英文摘要：
A collision-based hybrid algorithm for the discrete ordinates approximation of the neutron transport equation is extended to the multigroup setting. The algorithm uses discrete energy and angle grids at two different resolutions and approximates the fission and scattering sources on the coarser grids. The coupling of a collided transport equation, discretized on the coarse grid, with an uncollided transport equation, discretized on the fine grid, yields an algorithm that, in most cases, is more efficient than the traditional multigroup approach. The improvement over existing techniques is demonstrated for time-dependent problems with different materials, geometries, and energy groups.
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