Multigroup Neutron Transport using a Collision-Based Hybrid Method Dataset
收藏Zenodo2022-08-19 更新2026-05-25 收录
下载链接：
https://zenodo.org/record/7005482
下载链接
链接失效反馈官方服务：
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.
提供机构：
Zenodo创建时间：
2022-08-19
