Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection

摘要

We review recent work at Los Alamos to evaluate neutron, proton, and photonuclear cross section up to 150 MeV (to 250 MeV for protons), based on experimental data and nuclear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. For radiation protection, these data can be used to determine shielding requirements in accelerator environments, and to calculate neutron, proton, gamma-ray and radionuclide production. Illustrative comparisons of the evaluated cross section and kerma coefficient data with measurements are given.