A Review on Corrosion Mechanism in the Borosilicate Nuclear Waste Glass for Long-Term Performance Assessments in Geological Repository

Glass is an important material used for high-level nuclear waste (HLW) management, accommodates and immobilizes several constituents. The ability ot the nuclear waste glasses is to contain high-level radioactive wastes over the service life of a potential geologic repository. The corrosion of a complex waste glass is governed by two basic mechanisms, such as, ion exchange and hydrolysis. In the present review paper, leach rate experiments under accelerated pressure, temperature and controlled pH conditions are suggested to insight corrosion mechanism of complex nuclear waste glasses. The data obtained is required to be simulated, using geochemical codes to extrapolate corrosion of glass for long term performances assessments in the geological repository.