Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection
The authors 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.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE Office of Defense Programs (DP) (US)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 759286
- Report Number(s):
- LA-UR-98-4139; TRN: US0004331
- Resource Relation:
- Conference: International Meeting on Computational Methods in Track Structure Simulation in Physical and Biological Sciences, Theory and Applications, Oxford (GB), 09/10/1998--09/13/1998; Other Information: PBD: 10 Sep 1998
- Country of Publication:
- United States
- Language:
- English
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