Simulation of Nuclear Detection Capabilities in Portal Monitors

Year
1981
Author(s)
R.R. Nason - Sandia National Laboratory
Abstract
A technique for accurately predicting the response of a portal monitor to a given quantity of special nuclear material is described. The three dimensional Monte Carlo code MORSE is employed in the forward mode to calculate the response of large volume plastic scintillators. A technique is presented whereby the Monte Carlo calculation need be done only once to obtain the detection rate for a given source located anywhere within the detection volume.