Neutron Cross Section - Typical Cross Sections

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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