Document Type
Report
Publication Date
8-1990
Abstract
Neutron transport calculations were performed using the Monte Carol code, MCNP. The transport problem considered has a point source at high altitude (40 km). Since atmospheric density decreases with altitude, two-dimensional effects (cylindrical coordinates) can be important. Results were compared to those obtained with the SMAUG-II computer code, which performs mass-integral scaling of approximate fits to one-dimensional spherical discrete ordinates solutions. These comparisons show the importance of two-dimensional computations. The report discusses practical issues of applying MCNP to this problem, without code modifications and includes example input files for MCNP and for SMAUG-II. Computational modelling of neutron transport in the atmosphere is complicated by the variation of air density with altitude.
Recommended Citation
Culp, D. R., Monti, D. L., Shoemaker, J. R. & Wesley, D. (1990). Monte Carlo Simulation of Atmospheric Neutron Transport at High Altitudes Using MCNP. AFIT Report AFIT/EN-TR-90-5. https://scholar.afit.edu/docs/147
DTIC Accession Number
ADA226773
Document / Report Number
AFIT/EN-TR-90-5
Comments
See also the AFIT theses of co-authors Culp, Monti, Shoemaker and Wesley.
This work was sponsored by the Air Force Weapons Laboratory.