Thermal Stability of Glass with Simulators of Chloride Highly Radioactive Wastes

摘要

High temperature behavior of sodium-aluminum fluorophosphate glassa potential matrix for immobilisation of waste salt electrolyte from pyrochemical reprocessing of irradiated nuclear fuel (INF) has been studied. The glass crystallizes between 430 and 640 degrees C with formation of phosphate phases, which dissolve above 640 degrees C leading to homogenization of the glass. Similar transformations of the glass matrix due to heating from the decay of short-lived fission products may have a negative effect on properties of vitrified radioactive chloride wastes during storage in a repository.