Chemical durability and structural analysis of PbO–B2O3 glasses and testing for simulated radioactive wastes

Abstract

Abstract Lead borate based glass formulations with high chemical durability and lower melting temperatures compared to the currently used glasses were developed as candidates for the vitrification of radioactive waste. Properties including chemical durability, glass transformation temperature, and melting temperature were analyzed. The chemical durability of PbO–B2O3 glasses with PbO contents ranging from 30 to 80 mol% was determined. An average dissolution rate of 0.2 g m−2 day−1 was obtained for the composition 80PbO⋅20B2O3. These glasses were studied under simulation conditions and showed good potential as a vitrification matrix for radioactive waste management. Clear vitrified waste products containing up to 30 mol% SrO and 25 mol% Cs2O could be obtained. Leaching rates are about hundred times higher in low PbO glasses compared to high PbO glasses. These results are encouraging since they open up new horizons in the development of low melting temperature lead borate glass for waste immobilization applications.