[en] This report describes a workshop that was organised by the Swedish Nuclear Power Inspectorate (SKI) for assessment of the handling of near-field radionuclide retention processes by the Swedish Nuclear Fuel and Waste Management Company (SKB). The general objective with this type of meeting is to improve the knowledge and awareness of recent developments and to provide preliminary review comments. A number of SKB reports provided the general background for the workshop discussions. One report addresses the release of radionuclides from spent fuel, another the concentration limits related to radionuclide solubility and a third buffer radionuclide sorption and migration parameters. These reports comprise a basis for the handling of the spent fuel, solubility and sorption processes in new complete safety assessment SR-Can. The discussion and analysis of these background reports at the workshop therefore provide an essential element of preparation for the planned review of SR-Can. The review comments provided in this report are nonetheless of a preliminary character since the SR-Can report was not available at the time of the workshop and details about the incorporation of various potential safety features into the entirety of safety assessment were not known. The present report sets out the detailed objectives and format of the workshop in Section 2. Section 3 provides a high-level overview of processes that need to be taken into account. In Section 4, there is a brief discussion about the chemical and physical environment near the engineered barriers. Section 5 gives a more detailed description of spent fuel processes that affect the radionuclide releases. In Section 6, the key issues for radionuclide chemistry and the estimation of concentration limits for various radionuclides are discussed. Section 7 discusses radionuclide sorption and migration in the buffer and Section 8 presents overall conclusions from the workshop