Evaluation of the structural and radiation transmission parameters of recycled borosilicate waste glass system: An effective material for nuclear shielding.

Abstract

In the present study, the influence of B2O3 on the mechanical, physical, and radiation-response characteristics of waste borosilicate glass (BSG) is investigated. Four batches of the glass composite containing 0, 40, 50, and 60 wt % of B2O3 each were prepared and labelled as BB0, BB40, BB50, and BB60, respectively, using the popular melt- quench method. Through a series of experimental processes, the glasses’ density, hardness, and fracture toughness were measured. The mass attenuation coefficients (MACs), neutron removal cross-sections, and stopping powers of ions in the glasses were estimated using a mixture of Monte Carlo simulations and established theoretical models. By adding boron oxide to the WBSG (BB), a 39.50 % and 38.65 % increase in the density of the glass were observed for BB50 and BB60, respectively. About 9 % improvement was achieved in the hardness of the WBSG reinforced with B2O3. The MAC values were between the ranges of 0.0204–5.4610 cm2/g, 0.193–3.8959 cm2/g, 0.0189–3.4421 cm2/g, and 0.0186–3.0347 cm2/g for BB, BB40, BB50, and BB60, respectively, for gamma photons having energies within 0.015–15 MeV range. Also, the half-value layers for the same gamma photons energy range fell within the ranges of 0.053–14.19, 0.064–12.747, 0.061–10.98, and 0.07–11.226 cm for BB, BB40, BB50, and BB60, respectively. The increase in the boron oxide content in WBSG reduced the effective atomic number of the glass. The present glasses offer cheap and effective alternatives as gamma radiation protection barriers to some recently developed and commercial shielding glasses. The inves tigated glasses are recommended as cheap, strong, and effective attenuators for gamma, fast neutron, and light and heavy ion radiation