Abstract
In this study, it was investigated the neutron shielding performance of cement mortar with respect to different replacement ratios of liquid crystal display (LCD) waste glass powder in the mix. The LCD waste glass powder was an industrial by-product manufactured from the Republic of Korea, and the substitution level was 0%, 10%, and 20% by weight of the binder content. Prior to the evaluation of shielding capability, experimental works were performed to ensure the stability of LCD-mixed specimens, such as the development of strength, and quantitative phase analysis with thermogravimetric analysis (TGA). As a result, it was found that the mortar incorporating the LCD waste glass powder with about 13 μm of an average diameter showed a pozzolanic activity in the hydration periods, during which the strength at 28 days for the OPC-LCD mixtures was higher than that for OPC solely specimen. As for a neutron shielding of mortars, the thermal neutron shielding was enhanced with increasing content of the LCD waste glass powder in the specimens due to the presence of boron oxides (B2O3) in the binder. The capacity for LCD-mixed mortars in the thermal neutron shielding was achieved 1.18–1.23 times higher level for LCD-free mortar, depending on the LCD replacement ratio. Thus, LCD waste glass powder can be one of the alternative options for a binder in radiation shielding applications.
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