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

Abstract

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.

Open PDF

Document Details

Document Type
Technical Report
Publication Date
Aug 01, 1989
Accession Number
ADA210999

Entities

People

  • Howell Caton

Organizations

  • Ballistic Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies
  • Weapons Technologies

DTIC Thesaurus Topics

  • Armored Vehicles
  • Crystal Structure
  • Detectors
  • Free Field
  • Gamma Rays
  • Geometry
  • Production
  • Radiation
  • Radiation Protection
  • Radiation Shielding
  • Radiative Transfer
  • Scattering
  • Security
  • Shielding
  • Transport Ships
  • Vehicles
  • Weapons

Fields of Study

  • Physics

Readers

  • Computer Programming and Software Development.
  • Electromagnetic Wave Scattering and Antenna Radiation Engineering
  • Nuclear and Radiation Engineering.