Development Of High-Waste Loaded High-Level Nuclear Waste Glasses For High-Temperature Melter

In this paper the authors have attempted to determine the optimum formulations of nuclear waste glasses for maximum waste loading in a high-temperature melter. Density and leachability of the product were the two properties put in context. Proportions of neutralised current acid waste and SiO2 in the resulting glass were idemtified by simulation method. Liquidus temperature model was used to determine crystallinity for different amounts of alkali oxide additives. Based on these, glasses with Na2O and Li2O added were formulated and tested in a high temperature melter at 1550 deg C. Crystallinity was lower in formulations with higher contents of alkali and blend waste.