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Abstract Incorporation of mineral and ores as fine aggregate additives was investigated for its effect on the neutron and gamma-ray shielding properties of cement mortar. Five mortar mixtures have been prepared with different proportions of additives ranging from 0% to 30% of the cement mass by weight. Evaluation of gamma-ray attenuation was both measured experimentally and computed by means of a software. The measurements have been carried out for ores and mortar samples using 59.54, 662 and 1332 keV gamma photons. The theoretical values have been calculated in the energy range from 10 keV to 1 GeV. Many shielding parameters such as mass attenuation coefficient (μ/ρ), effective atomic number (Z eff) and corresponding electron density (N eff) and gamma–ray kerma coefficients (k γ) have been determined. The calculated values are in good agreement with the observed values. Furthermore, the macroscopic fast neutron removal cross-sections (Σ R , cm−1) have also been calculated by means of a software. The results of this study showed that the gamma-ray and neutron attenuation parameters of the studied mortar samples do not display any significant variation due to the addition of ores and minerals at the investigated mixing proportion (30% of the cement mass by weight). [ABSTRACT FROM AUTHOR]

In this study, gamma ray and neutron shielding properties of Al25Zn alloy samples prepared by induction melting technique with the composition of (75− x)Al–25Zn– x Ti (x = 0, 0.01, 0.1 and 1 wt %) were investigated theoretically and experimentally. The mass attenuation coefficients (μ/ρ) of the alloys were measured experimentally with a coaxial high purity germanium (HPGe) detector at 59.54, 662, 1173 and 1332 keV photon energies. The theoretical values have been calculated in the energy ranging from 1 keV to 1 GeV using WinXcom database. Afterwards, the obtained mass attenuation coefficient values have been utilized for determination of some shielding parameters such as half value layer (HVL), mean free path (MFP), effective atomic number (Z eff) and gamma–ray kerma coefficients (k γ). The calculated values are in good agreement with the observed values. Furthermore, the macroscopic fast neutron removal cross-sections (Σ R , cm−1) have also been calculated. Ti1 coded alloy sample containing 1% Ti was found to have maximum radiation protection efficiency (RPE) and neutron removal cross section (ΣR, cm−1) as well as the smallest half value layer (HVL) and mean free path (MFP) values. Hence, the results of this study showed that Ti1 alloy specimen has superior gamma and neutron radiation shielding performance among the other compared alloys. Image 1 • Radiation shielding performances of Ti-doped Al25Zn alloys were investigated. • Gamma kerma coefficients of alloys were determined. • The experimental measurements were carried out using HPGe detector system. • The experimental results are compared the WinXcom. • 1% Ti doped alloy is a promising candidate for gamma shielding applications. [ABSTRACT FROM AUTHOR]