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Comparison of CdZnTe neutron detector models using MCNP6 and Geant4

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Article number08008
<mark>Journal publication date</mark>10/01/2018
<mark>Journal</mark>EPJ Web of Conferences
Volume170
Number of pages5
Publication statusPublished
Original languageEnglish
Event5th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, ANIMMA 2017 - Liege, Belgium
Duration: 19/06/201723/06/2017

Conference

Conference5th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, ANIMMA 2017
CountryBelgium
CityLiege
Period19/06/1723/06/17

Abstract

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.