Attenuation Effect of Sample Container in Radioactivity Measurement by Gamma-ray Spectroscopy

The measurement of radioactivity in environmental samples containing natural radionuclides such as 238U, 232Th, and 40K gamma-ray spectrometry is the most common application. One widely used sample containers for measurements volumetric certain sizes cylindrical geometry. These can be made materials with different densities thicknesses. In this intention, study, effect container, which one many parameters affecting detector efficiency, was investigated. For purpose, acrylic polypropylene were examined. IAEA RGU-1, IAEA-RGTh-1 IAEA-RGK-1 standards uranium, thorium potassium analyzed spectrometric these densities. Additionally, since spectra geometry are taken by placing them on endcap, bottom thickness investigated changing materials. Different material evaluations using PHITS GESPECOR Monte Carlo simulation programs. Compatible results obtained a difference <5% between From outcome it concluded that when choosing container material, density should low possible especially thin.