[en] Vitrification is today the principal way of industrial scale management of high-level radioactive waste for transport, short and long-term interim storage and eventual deep geological disposal. Glass is used as containment matrix, because, if its composition is properly chosen, it has a high mechanical, chemical and radiation resistance and because it is the only known material, which due to its disordered atomic structure, is capable to incorporate at the same time the residual plutonium and uranium remaining after reprocessing and the minor actinides as well as the vast majority of the long-lived fission and activation products and process chemicals in a single solid phase. Current understanding of the complicated glass corrosion mechanism is high, suggesting that nuclear waste glass will resist complete corrosion for 1 to 100 million years and even after complete corrosion, a very large fraction of sparingly soluble actinides and long-lived fission products are retained in the altered glass. Further research is necessary in the details of our understanding and in model development to increase predictive credibility, considering that is the first time in science that the attempt is made to predict the performance of a material for more than hundredth of thousands of years. (author)