Radiation shielding capability of transparent lead borate Tellurite glass system

Document Type

Conference Proceeding

Publication Date

2023

Abstract

In this study, material characterization and radiation shielding efficiency of tellurium lead-borated glass composites with the molar composition 50H3BO3 - 10 Na2CO3 - (40-x) TeO2 − x PbO (where x=0, 5, 10, 15, 20 mol percent) was investigated across a wide energy range of 0.015-15 MeV. FTIR spectra confirmed the presence of BO3, BO4, TeO3, TeO4 compositional components. The measured mass attenuation coefficients (μm) for all prepared glasses ranged from 7.99 x10−2 – 8.88x10−2 g/cm2 at 0.662 MeV. Compared with the previously prepared glasses and other materials such as Barite and Portland concrete, the prepared glass samples have a higher mass attenuation coefficient and effective atomic number at the same energy and PbO mole %. The Geometric Progression (G-P) approximation was used to calculate the prepared samples’ exposure build-up factors (EBF). Fast neutron removal cross-sections ranging from 0.135 to 0.145 cm- 1for the variation of PbO concentrations 0-20 mol % were also obtained. Based on the obtained results, the prepared tellurium lead-borate glass composite developed in this work has more enhanced shielding capabilities, enabling the construction of a highly efficient, transparent gamma-ray and fast neutron shield for medical radiation shielding applications.

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