Comparison of CdZnTe neutron detector models using MCNP6 and Geant4

• Published in: EPJ Web of conferences Vol. 170; p. 8008
• Main Authors: Wilson, Emma, Anderson, Mike, Prendergasty, David, Cheneler, David
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Les Ulis EDP Sciences 01.01.2018
• Subjects: Cadmium zinc tellurides; Computer simulation; Detectors; Intermetallic compounds; Modelling; Neutral particles; Neutron counters; Neutron flux; Neutrons; Sensors; Zinc telluride; United Kingdom > UK
• ISSN: 2100-014X; 2101-6275; 2100-014X
• DOI: 10.1051/epjconf/201817008008

The production of accurate detector models is of high importance in the development and use of detectors. Initially, MCNP and Geant were developed to specialise in neutral particle models and accelerator models, respectively; there is now a greater overlap of the capabilities of both, and it is therefore useful to produce comparative models to evaluate detector characteristics. In a collaboration between Lancaster University, UK, and Innovative Physics Ltd., UK, models have been developed in both MCNP6 and Geant4 of Cadmium Zinc Telluride (CdZnTe) detectors developed by Innovative Physics Ltd. Herein, a comparison is made of the relative strengths of MCNP6 and Geant4 for modelling neutron flux and secondary γ -ray emission. Given the increasing overlap of the modelling capabilities of MCNP6 and Geant4, it is worthwhile to comment on differences in results for simulations which have similarities in terms of geometries and source configurations.