High Altitude Atmospheric Radiation Transport Calculations
Abstract
This report contains the results of MORSAIR code Monte Carlo calculations of neutron and secondary gamma transport in a real two-dimensional variable density atmosphere. These data were generated so that an assessment could be made of the adequacy of mass integral scaling of uniform air calculations in defining radiation environments in the atmosphere. Unclassified fission and thermonuclear source spectra were used in the calculations at source altitudes from 5 to 80 kilometers. Silicon and tissue doses as well as the total fluences were calculated for both neutrons and secondary gammas.
Document Details
- Document Type
- Technical Report
- Publication Date
- Aug 01, 1976
- Accession Number
- ADA030817
Entities
People
- James C. Eamon
Organizations
- Kaman Corporation