Abstract:
In this study, waste cathode ray tube screen glass (WCSG) doped with Li2O and Y2O3 was prepared and investigated for physical properties, structural definition, and their charged radiation and neutron shielding competence through a series of experimental and theoretical approaches. Using the cold isostatic press method, WCSGinfused Li2O + Y2O3 composite glass ceramic samples were prepared. The Li2O + Y2O3 composite concentrations were varied from 0 (STV), 10 (STV-YLI1), and 20 (STV-YLI2) wt%. The prepared glasses were sintered, and their crystal structure and surface microstructure were probed using the XRD technique and SEM images. The prepared samples were analysed for their radiation shielding abilities, starting from the computation of parameters related to their interaction with charged radiation and neutrons. The ESTAR, PSTAR, ASTAR, and STRIM software. In addition, the fast neutron (FN) removal cross section (FNRCS) and thermal neutron (TN) total crosssection (sigma tot) for the prepared glasses were evaluated theoretically using established models. The XRD spectra of the samples showed distinct crystalline structure and the formation of glass-ceramic material. The addition of the Li2O + Y2O3 composite reduced surface pores, increased hardness, and increased the sample density. The Vickers hardness values were calculated as 495, 527, and 552 HV for the STV, STV-YLi1, and STV-YLi2 samples, respectively, while the corresponding densities were 2.506, 2.592, and 2.634 g/cm3. The addition of Li2O + Y2O3 to the WCSG slightly improved the glass-ceramic system's charged particle shielding ability. The FNRCS of STV, STV-YLi1, and STV-YLi2 are 0.0775, 0.0827, and 0.0867 cm-1 respectively. The ability of the prepared glass ceramics to absorb fast and thermal neutrons improved with the addition of Li2O + Y2O3. The materials are recommended for use as environmental friendly radiation shields.
