NEUTRON-PHOTON MULTIGROUP CROSS-SECTIONS FOR NEUTRON ENERGIES LESS-THAN-OR-EQUAL-TO 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, **1**0B, **1**1B, carbon, oxygen, silicon, calcium, chromium, iron, and nickel are described. 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 equals 3. 6g multiplied by (times) cm** minus **3) shield are presented. The energy distribution of the source neutrons is approximately that from a Li(D, n) neutron radiation damage facility.