Objective Reprocessing of spent fuel yielded already more than 1, 150 cubic metres of COMEGAHLW glass. Geological disposal of vitrified waste is worldwide studied as a safe option. Long-term predictions of the glass performance are based on results from laboratory tests. Especially the public experiences these predictions as unreliable, "since derived from irrealistic labotory tests". In the proposed project, the reliability of the predictions will be evalued by confrontation with the results of an in situ corrosion test of alpha-active COMEGA HLW glass, performed in realistic conditions (temperature, gamma radiation, backfill materials). Three corrosion tubes will be operated. Both the global glass dissolution and the specific radionuclide release and migration will be measured. If in the situ results agree with the laboratory results, the in situ test will be a small scale demonstration test of the good of the COMAGA HLW glass. Fields of science engineering and technologymaterials engineeringengineering and technologyenvironmental engineeringenergy and fuelsnatural scienceschemical sciencesnuclear chemistryradiation chemistry Programme(s) FP5-EAECTP C - Research and training programme (Euratom) in the field of nuclear energy (1998 to 2002) Topic(s) 2.1.2.-2.1.5 - Long-term behaviour of repository systems Call for proposal Data not available Funding Scheme CSC - Cost-sharing contracts Coordinator BELGIAN NUCLEAR RESEARCH CENTRE EU contribution No data Address 200,Boeretang 200 2400 MOL Belgium See on map Total cost No data Participants (2) Sort alphabetically Sort by EU Contribution Expand all Collapse all COMMISSARIAT A L'ENERGIE ATOMIQUE France EU contribution No data Address CEA Marcoule / Valrho, Marcoule 30207 BAGNOLS-SUR-CEZE See on map Total cost No data GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT (GRS) MBH Germany EU contribution No data Address Theodor-Heuss-Strasse 4 38011 BRAUNSCHWEIG See on map Total cost No data
