Our contribution focuses on the release of fission gases during the dissolution process of two different types of spent nuclear fuel, i.e. UO_X and (U, Pu)OX mixed-oxide fuels, in order to identify and quantify the role of fission gas release rates as an indicator of radionuclide source terms. Within our work, it is shown that, independent of the type of spent nuclear fuel, a comparable, fast initial release of fission gases is evident in all experiments.

This paper presents an experimental investigation of uranium release from spent nuclear fuels under conditions expected in a deep geological repository.