Evaluates neutron and gamma radiation for material detection in mobile platforms, indicating safety parameters for operations.
Compact neutron generators enable prompt gamma neutron activation analysis as an effective technique for subsurface material identification in applications such as unexploded ordnance and land mine detection. Their integration into mobile platforms introduces complex mixed neutron-photon radiation fields that require quantitative evaluation. In this study, neutron and secondary gamma radiation transport from a compact deuterium-tritium neutron generator integrated into the optionally manned ground vehicle TAERO, a platform adapted for off-road demining operations, is investigated using Monte Carlo simulations.Spatial distributions of neutron flux and gamma dose rate are analyzed at locations corresponding to the vehicle operator and onboard electronic systems within a material-representative vehicle geometry. Neutron-induced displacement damage in silicon is additionally evaluated as a metric of radiation exposure for electronic components. The analysis focuses on the influence of distance, structural scattering, and local shielding on radiation field characteristics and on the derivation of distance-dependent dose parameterizations relevant to operational deployment.The presented approach establishes a framework for characterizing the radiation exposure associated with compact neutron-based sensing systems deployed on mobile demining platforms. These outcomes are employed to establish operational limits and safety-relevant constraints for the engineering design and integration of mobile neutron-based systems.
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Nowakowski et al. (2026) studied this question.
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