Assessment of SiO2-B2O3-Na2O-TiO2-Fe2O3 Glass System for the Vitrification of High-Level Acidic Radioactive Liquid Waste

A five-component glass system, SiO2-B2O3-Na2O-TiO2-Fe2O3, has been assessed as a durable host to immobilize High-level Liquid Waste (HLW) generated during the reprocessing of spent nuclear fuel. Simulated vitrified waste products (SVWP) were prepared on a laboratory scale, and process parameters and product quality were assessed for suitability by varying the composition of HLW. The process parameter and product quality were evaluated by assessing different properties such as pouring temperature (T, °C), density (ρ, g/cm3), glass transition temperature (Tg, °C), surface homogeneity, phase purity, and chemical durability/leach rate (LR, g cm−2 day−1). Glass composition has been compared with the literature; accordingly, with the product's salient features, the optimized process parameters are recommended for industrial use.