MONTE CARLO STUDIES OF GAMMA-RAY AND NEUTRON TRANSPORT IN INFINITE HOMOGENEOUS MEDIA
Abstract
Two point-source, infinite-medium Monte Carlo codes were written for the IBM 704 computer. The codes simulate respectively gamma-ray and neutron transport from a monoenergetic source. A detailed description, including importance sampling methods, is given. Results showed good agreement with moments-method calculations for the same geometry. Calculations for 6-Mev gamma rays in tin provide data on the contribution of annihilation radiation to both the buildup factors and energy spectra. Calculations for 1-Mev gamma rays in water are also presented. The results of calculations for 6-Mev source neutrons in water show a peak in the energy spectrum which is found to be due to single scattering of source particles from oxygen. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Nov 01, 1961
- Accession Number
- AD0265596
Entities
People
- Millard L. Wohl
- Theodore E. Fessler
Organizations
- National Aeronautics and Space Administration