Characterization of a Portable Neutron Coincidence Counter

Year
2006
Author(s)
H. Menlove - Los Alamos National Laboratory
William S. Charlton - TX A&M University
Angela L. Thornton - Oak Ridge National Laboratory
C. D. Rael - Los Alamos National Laboratory
Angela Thornton - Los Alamos National Laboratory
W. Charlton - Los Alamos National Laboratory
Abstract
Neutron coincidence counting is an important passive, nondestructive-assay method that can be used to quantify the amount of plutonium in bulk samples. During the fission process, neutrons are emitted in multiplets. Because these neutrons are emitted practically simultaneously, they create a useful signature that can be used to identify a particular nuclear material. A new portable neutron coincidence counter was has been developed to assist inspections performed in a variety of laboratory and field environments. The purpose of this new detector system is to identify nuclear material based on its coincident neutron signature. In order to characterize this system, various measurements were performed. In addition, an analysis was performed by comparing the measured data to both the data given by an MCNPX (Monte Carlo N-Particle eXtended) model of the detector system and the data from neutron coincidence point model. The results of this analysis will be used to create a reference model that can be used to rapidly quantify the amount of nuclear material present in a given sample with some confidence.