Synergistic effects of lead borosilicate waste glass on the mechanical and radiation shielding properties of cement-bitumen composites.

Abstract

This study investigates the radiation shielding performance of lead borosilicate waste glass when incorporated as an additive into cement-bitumen composites. The utilization of lead borosilicate glass, a byproduct of industrial processes, offers a dual advantage: it enhances the gamma-ray attenuation capacity of the composite achieving a mass attenuation coefficient of 7.85 × 10⁻² cm²/g and simultaneously contributes to the sustainable management of radioactive waste by improving the compressive strength to 32.9 MPa. Cement-bitumen mixtures were prepared with varying concentrations of the waste glass and evaluated through both experimental measurements and theoretical modeling. The linear attenuation coefficients demonstrated a marked improvement in shielding efficiency with increasing lead content. Computational tools, including XCOM and Geant4, were employed to simulate photon interactions and validate the experimental findings. The simulation results were in strong agreement with experimental data, confirming the enhanced attenuation properties at higher glass concentrations. These findings suggest that lead borosilicate waste glass is a promising additive for improving the gamma radiation shielding properties of cement-bitumen matrices, with potential applications in nuclear waste immobilization and radiation protection. Furthermore, the approach promotes sustainable recycling of industrial waste, aligning with environmental conservation goals. Further research is recommended to optimize glass loading and assess the long-term durability and structural performance under diverse environmental conditions.