Accession Number:

ADA210999

Title:

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

Descriptive Note:

Final rept.

Corporate Author:

ARMY BALLISTIC RESEARCH LAB ABERDEEN PROVING GROUND MD

Personal Author(s):

Report Date:

1989-08-01

Pagination or Media Count:

16.0

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.

Subject Categories:

  • Radioactivity, Radioactive Wastes and Fission Products

Distribution Statement:

APPROVED FOR PUBLIC RELEASE