Physical, structural and nuclear radiation shielding behaviour of xBaO-(0.30-x)MgO-0.10Na2O-0.10Al2O3-0.50B2O3 glass matrix

Abstract

In the present investigations, six cylindrical shaped glass sample having chemical composition x BaO-(0.30-x) MgO-0.10Na2O-0.10Al2O3-0.50B2O3 (x = 0.05, 0.10, 0.15, 0.20, 0.25 and 0.30 mol fraction) were prepared by melt quenching technique. The density, molar volume, oxygen packing density (OPD), oxygen molar volume (OMV), Poisson's ratio, barium inter ionic distance, Polaron radius and field strength were calculated for the prepared glass samples. The values of linear attenuation coefficients (LAC) were measured experimentally by using narrow beam transmission geometry in the gamma photon energy range of 59.54–1332 keV. In order to ascertain the application of the prepared glasses in the field of radiation protection and design, the values of LAC were used to calculate various gamma ray interaction parameters namely half value layer (HVL), Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), effective atomic number (Zeff), electron density (Ne) and Exposure Buildup Factors (EBFs). The values of fast neutron removal cross sections (∑R cm−1) were also calculated for the prepared glass matrix. The theoretical values of attenuation parameters were determined using online software Phy-X/PSD and FLUKA (Monte-Carlo) simulation code. Excellent agreements have been observed between experimental, theoretical and simulation results for the prepared glass samples. Furthermore, the radiation shielding properties for the prepared glass samples were compared with conventional used concretes and commercial radiation shielding glass (RS253 G-18). On the basis of the obtained results, it has been reported that the prepared glass samples possess satisfactory physical reliability and superior shielding efficiency against gamma rays and fast neutrons as compared to conventional/commercial shielding materials.