Enhancing accuracy in gamma-ray spectrometry: mathematical methodology for self-attenuation correction in radioactive samples analysis

This study introduces a methodology for correcting self-attenuation effects in γ-ray energy range 59 to 2614 keV.

Using simulation techniques, we examine the impact of material characteristics on attenuation. A comparative analysis with a reference standard sample of identical geometry but differing matrix and density enables the estimation of correction factors. Peak efficiency calculations include various matrices, including that present in nuclear fuel cycle and environmental field with densities ranging from 1 to 2 g/cm³.

Monte Carlo simulations are employed to calculate peak efficiencies for epoxy reference materials within the same density and energy range. The self-attenuation correction factor is obtained by comparing the peak efficiencies of the assayed materials with those of the reference samples. The study discusses factors influencing self-attenuation correction, emphasizing its significance in accurate radionuclide measurements.

This method provides a standardized approach for calibrating and analyzing radionuclides in the materials present in the nuclear fuel cycle and environmental or NORM soil samples, detailing considerations for accurate measurement and correction of self-attenuation effects.