The observed value of the removal cross-section is, in fact,
roughly equal to 2/3 of the total Rt (cm1), (scattering and capture)
cross-section of the given material for neutrons having
energies in the range of 6–8 MeV (Glasstone and Sesonske,
1986). If concrete contains sufficient moderating material, the
attenuation of neutrons will be determined by this removal
process.