Multigroup Neutron Transport using a Collision-Based Hybrid Method Dataset
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资源简介：
G = 361 Energy Group dataset for the "Multigroup Neutron Transport using a Collision-Based Hybrid Method" paper (under review) by Whewell et al. Included is the total, scattering, and fission cross section matrices for the G = 361 uranium oxide problem and the energy group bounds for G = 361, 300, 240, 180, 150, 120, 90, 60, and 30.
创建时间：
2022-08-18
