Objective The basic objectives of this programme were tostudy the corrosion mechanisms of a selected number of waste glasses in clay and clay water solutions, which are believed to be the main components of interaction in the long term. At the same time, the influence of the corrosion products from the canister or overpack, and the presence of a gamma-irradiation field have been included in the programme. Another important part of the programme was the performance of in situ tests with simulated waste forms, which would yield validation of the observations made in laboratory tests. The data obtained would be used to estimate the long term corrosion behaviour of the waste glass, and to identify its barrier function with respect to the release of radioactive elements into the surrounding clay rock. These data also should form the basis for future modelling efforts to predict the performance of the glasses in disposal conditions. The laboratory and in situ interaction with Boom clay has been investigated for 4 reference waste glasses. Boom clay is the candidate host rock medium for geological disposal of radioactive waste studied in Belgium. The experimental test durations were up to 4 years. Fields of science engineering and technologyother engineering and technologiesnuclear engineeringnuclear waste managementengineering and technologymaterials engineering Programme(s) FP1-RADWASTOM 3C - Research and development programme (Euratom) on the management and storage of radioactive waste, 1985-1989 Topic(s) Data not available Call for proposal Data not available Funding Scheme CSC - Cost-sharing contracts Coordinator BELGIAN NUCLEAR RESEARCH CENTRE Address 200,herrmann debrouxlaan 40-42 1160 Bruxelles Belgium See on map EU contribution € 0,00
