This report gives a summary of literature and SCK•CEN data pertaining to the dissolution behaviour of vitrified (V)HLW waste in generic geological disposal conditions, with special attention to the systems that are dominated by the presence of Ordinary Portland Cement and its typical high pH.
It contains a description of the vitrified waste alteration and dissolution mechanisms, leading to the release of radionuclides. Both results found in the open literature and experimental and modeling results generated in the framework of the Belgian R&D programme are presented.
The available information shows that similar glass dissolution mechanisms occur at near-neutral and high pH, but their relative importance is different.
|Number of pages||133|
|State||Published - 30 Jun 2019|
|Publisher||Studiecentrum voor Kernenergie|