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.
Highlights
In order to maintain and improve safety standards within the nuclear sector, more emphasis is placed on novel detector materials and configurations for use in nuclear power, decommissioning, and security, as well as for other applications
Cadmium zinc telluride (CdZnTe, or CZT) radiation detectors are widely used in γ-ray spectroscopy as a roomtemperature, semiconductor-based detector
This is of particular use as Cadmium Zinc Telluride (CdZnTe) detectors possess an improved energy resolution, when compared to scintillation-based radiation detectors, and, unlike high-purity germanium, has a sufficiently wide band-gap to significantly reduce thermal excitation of electrons across the gap, and CdZnTe detectors do RESULT OF NEUTRON CAPTURE ON A CDZNTE DETECTOR
Summary
In order to maintain and improve safety standards within the nuclear sector, more emphasis is placed on novel detector materials and configurations for use in nuclear power, decommissioning, and security, as well as for other applications It is for this reason that the capability to accurately mathematically model detector response is essential; in the first instance this would be a check of the applicability of the detector for the planned purpose. An understanding of the difference capabilities and, where appropriate, direct comparisons of these tools is essential, as it give an indication of which is more appropriate in a given circumstance Previous work in this field has compared the capabilities of MCNP and Geant in areas including medicine [3], nuclear power [4], and security [5], the development of both MCNP and Geant, and the associated cross-section data, is on-going such that the individual capabilities of the codes vary. This is of particular use as CdZnTe detectors possess an improved energy resolution, when compared to scintillation-based radiation detectors, and, unlike high-purity germanium, has a sufficiently wide band-gap to significantly reduce thermal excitation of electrons across the gap, and CdZnTe detectors do TABLE I THE HIGHEST INTENSITY PROMPT SECONDARY γ -RAYS PRODUCED AS A
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