Nuclear Cross Sections: Be
One-group (thermal + fast) neutron cross-sections for key nuclides used in reactor physics — absorption (sigma_a), fission (sigma_f), capture (sigma_c), scattering (sigma_s), and transport cross-sections in barns. Covers fissile/fertile actinides (U-233, U-235, U-238, Pu-239, Pu-241, Th-232), moderators (H2O, D2O, graphite, Be), structural materials (Fe, Cr, Ni, Zr, Al), and neutron poisons (B-10, Cd, Xe-135, Sm-149, Gd). Data from ENDF/B-VIII.0 and Lamarsh.
| nuclide | energy group | notes | nuclide category | nuclide type | sigma a barns (barns) | sigma c barns (barns) | sigma s barns (barns) | unit |
|---|---|---|---|---|---|---|---|---|
| Be | fast | Fast group. (n,2n) reaction threshold ~1.84 MeV contributes extra neutrons. | moderator | moderator | 0.001 | 0.001 | 2.8 | barns |
| Be | thermal_2200ms | Beryllium. Moderating ratio=130. Also neutron reflector; (n,2n) reaction important. | moderator | moderator | 0.0092 | 0.0092 | 6.1 | barns |
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