Analysis by Monte Carlo of thermal neutron flux from a 241Am/9Be source for a system of trace analysis in materials

Abstract

Design of an enhanced thermal neutron source for use in trace detection in substances or materials, through NAA method.• The thermal neutron irradiation system is using a 241 Am/ 9 Be source.• Different configurations of polyethylene cylinders were simulated to choose the one giving the highest thermal neutron flux.• The performance was evaluated with the MCNP6 code and validated with laboratory measurements with a miniature BF 3 detector.

Detection of antipersonnel landmines containing ANFO-based explosive: A review

“…Recently, neutron activation analysis has emerged as a strategy to determine the elemental composition of explosives. This, thanks to the gamma rays emission that characterize the interactions between neutrons and nuclei of atoms present in explosive compounds [32]. Taking this principle into account, Cevallos et al simulated three configurations varying the geometry of the device, material thickness, number, position, and size of the gamma-ray detectors.…”