Adaptive gamma spectrum based on neutron transport algorithm

Neutron activation γ-energy spectrometry is widely applied in nuclear physics, environmental monitoring, and radiation safety. However, its practical use is hindered by high experimental costs, limited samples, and the excessive computational load and time consumption of traditional Monte Carlo simulations. To address these issues, this study proposes a method for rapid and accurate γ-spectrum generation based on a neutron transport algorithm, developing a system integrated with a LaBr3 detector and an isotopic neutron source. The computational model simulates transient neutron activation processes such as neutron scattering, photon scattering, and nuclide de-excitation to generate photons efficiently. Using MATLAB, nuclear data from the ENDF/B-VII database covering 70 nuclides were processed, and the model was verified with stainless steel samples. Comparison results show that the simulated γ-spectra are highly consistent with experimental measurements, with characteristic peaks matching well in the 0–6000 keV range, confirming the model’s validity and applicability for alloy material analysis.