This is the investigation into the generation of high-fidelity multigroup multiband cross sections from Monte Carlo neutron transport simulations. Previous methods for generating multigroup multiband (MGMB) cross sections, and multigroup cross sections, assume an approximate shape for the scalar flux. This approximate flux shape is the product of an energy-dependent spectrum and a cross-section-dependent self-shielding factor for the material of interest. Since, these methods assume a scalar flux a priori, the cross sections generated may not be sufficiently consistent with the actual scalar flux of any particular problem. Instead, in our approach we tally both the reaction rate and the flux for each energy group and cross section magnitude band using the Mercury Monte Carlo particle transport code and compute the group-band cross sections from these tallies. This approach eliminates the need for assuming a flux by using a Monte Carlo simulation to calculate these cross sections. The increased physical fidelity of MGMB also requires more data storage, since more than one cross section value needs to be stored per energy group. However, this storage tradeoff could be mitigated by using less energy groups.

这是对由蒙特卡洛中子传输模拟产生的高保真多组多频带截面的研究。用于生成多组多频带（MGMB）横截面和多组横截面的先前方法采用标量通量的近似形状。这种近似的通量形状是目标材料的能量相关光谱和横截面相关自屏蔽因子的乘积。因为，这些方法假设一个标量通量的先验，生成的横截面可能与任何特定问题的实际标量通量都不足够一致。取而代之的是，在我们的方法中，我们使用Mercury Monte Carlo粒子传输代码对每个能量组和横截面幅度带的反应速率和通量进行了计算，并从这些计数中计算了基带横截面。通过使用蒙特卡洛模拟来计算这些横截面，这种方法消除了假设磁通量的需要。MGMB物理保真度的提高还需要更多的数据存储，因为每个能量组需要存储一个以上的横截面值。但是，可以通过使用较少的能源组来减轻这种存储折衷。