Neutron-Photon Multigroup Cross Sections for Neutron Energies 60 MeV

Multigroup cross sections (47 n groups, 21 gamma-ray groups) in ANISN format for neutron energies from thermal to 60 MeV and for the elements hydrogen, ¹⁰B, ¹¹B, carbon, oxygen, silicon, calcium, chromium, iron, and nickel are described. A P₅ Legendre expansion is used at energies , and a P₃ Legendre expansion is used at energies . Below 14.9 MeV, the cross sections are from the Radiation Shielding Information Center's fusion energy cross-section library. Above this energy, differential elastic scattering cross-section data from optical model calculations are used, and differential nonelastic scattering data from the intranuclear-cascade-evaporation model are used. Calculated results of the dose equivalent versus depth in the shield from a point isotropic source at the center of a 366-cm-thick spherical shell heavy concrete (density = 3.6 g cm⁻³) shield are presented. The energy distribution of the source neutrons is approximately that from a Li(D, n) neutron radiation damage facility.