Typical Cross Sections
In the following, some cross sections which are of importance in a nuclear reactor are given. The thermal cross-section is averaged using a Maxwellian spectrum and the fast cross section is averaged using the uranium-235 fission spectrum. The cross sections are taken from the Jeff-3.1.1 library using Janis software.
| Thermal cross section (barn) | Fast cross section (barn) | ||||||
| Scattering | Capture | Fission | Scattering | Capture | Fission | ||
| Moderator | H-1 | 2E+1 | 2E-1 | - | 4E+0 | 4E-5 | - |
| H-2 | 4E+0 | 3E-4 | - | 3E+0 | 7E-6 | - | |
| C (nat) | 5E+0 | 2E-3 | - | 2E+0 | 1E-5 | - | |
| Structural materials, others | Zr-90 | 5E+0 | 6E-3 | - | 5E+0 | 6E-3 | - |
| Fe-56 | 1E+1 | 2E+0 | - | 2E+1 | 3E-3 | - | |
| Cr-52 | 3E+0 | 5E-1 | - | 3E+0 | 2E-3 | - | |
| Ni-58 | 2E+1 | 3E+0 | - | 3E+0 | 8E-3 | - | |
| O-16 | 4E+0 | 1E-4 | - | 3E+0 | 3E-8 | - | |
| Absorber | B-10 | 2E+0 | 2E+3 | - | 2E+0 | 4E-1 | - |
| Cd-113 | 1E+2 | 3E+4 | - | 4E+0 | 5E-2 | - | |
| Xe-135 | 4E+5 | 2E+6 | - | 5E+0 | 8E-4 | - | |
| In-115 | 2E+0 | 1E+2 | - | 4E+0 | 2E-1 | - | |
| Fuel | U-235 | 1E+1 | 6E+1 | 3E+2 | 4E+0 | 9E-2 | 1E+0 |
| U-238 | 9E+0 | 2E+0 | 2E-5 | 5E+0 | 7E-2 | 3E-1 | |
| Pu-239 | 8E+0 | 4E-2 | 7E-2 | 5E+0 | 5E-2 | 2E+0 | |
Read more about this topic: Neutron Cross Section
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