Using MCNP Code for Neutron and Photon Skyshine Analysis

Autor: Zharkov, V P, Dikareva, O F, Kartashev, I A, Kiselev, A N, Netecha, M E, Nomura, Y, Tsubosaka, A
Zdroj: Journal of Nuclear Science and Technology; March 2000, Vol. 37 Issue: Supplement 1 p603-605, 3p
Abstrakt: The MCNP Monte-Carlo code was used for the investigation of the sensitivity of neutron and neutron-induced secondary photon dose rate, total and thermal neutron fluxes and space-energy distributions to energy and angular distribution of radiation source, to thickness and composition of the ground, air density (including it changing with height), humidities of air and ground, thermalization effects, detector’s dimension and its disposal above the ground level. The calculations were performed with the assumption that the source or released radiation into the atmosphere can be treated as a point source and the source containment structure has a negligible perturbation on the skyshine radiation field.
Databáze: Supplemental Index