Radiation Transport Calculations of a Simple Structure Using the Vehicle Code System with 69-Group Cross Sections and the Monte-Carlo Neutron and Photon Code
ARMY BALLISTIC RESEARCH LAB ABERDEEN PROVING GROUND MD
Pagination or Media Count:
The 58-Group Cross-Sections used in VCS calculations do not adequately described secondary gamma production in steel. In response, Oak Ridge National Laboratory ORNL has compiled a set of cross sections with 69 energy groups. This report documents an escalation of the 69 group cross sections on a simple steel box with various radiation liners. Also evaluated is the Monte Carlo Neutron and Photon Transport Code MPNP. Keywords Vehicle code system Radiation transport Morse code.
- Radioactivity, Radioactive Wastes and Fission Products