Final Activity Report: Project MICADO. Model uncertainty for the mechanism of dissolution of spent fuel in nuclear waste repository

This report summarizes the final results of the MICADO project ('Model uncertainty for the mechanism of dissolution of spent fuel in nuclear waste repository'). The evaluation of the long term performance of the spent fuel relies on the development of theoretical and sometimes semiempirical models which can be combined with more general safety assessment models allowing repository barrier performance predictions for overall repository performance assessment (PA). The coordinated action MICADO assesses the uncertainties in models describing the dissolution processes of spent nuclear fuel in a repository for geological time periods. The objective is to find out whether international research has now provided sufficiently reliable models to assess the corrosion behaviour of spent fuel in groundwater and by this to contribute to answering the question whether the highly radioactive used fuel from nuclear reactors can be disposed of safely in a geological repository.