Filtered generated 213 hits.
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2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption
For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...
Content type: Publications -
2008:57 Discrete Feature Model (DFM) User Documentation
This manual describes the DiscreteFeature Model (DFM) software package for modelling groundwater flow and solute transport in networks of discrete features. A discretefeature conceptual model represents fractures and other waterconducting features around a repository as discrete conductors surrounded by a rock matrix which is usually treated as impermeable. This approximation may be valid for...
Content type: Publications -
2025:02 INCLUDE: Including (local) stakeholder participation in the regulatory mission – a future challenge
SSM perspective Background The primary focus of SSM’s communication with stakeholders in relation to the disposal of spent nuclear fuel and nuclear waste has for several years been on formal consultation processes surrounding the Swedish nuclear power industry’s research and development programme as well as SKB’s licence applications under the Nuclear Activities Act. Following licensing by...
Content type: Publications -
2026:04 3D Discrete Element Modelling of Fluid Injection Induced Fault Slip in Argillaceous Rock – Mt.Terri Fault Slip Experiment
SSM perspective Background and objective It is a well-known phenomenon that artificial increased in pore pressure at depth, due to subsurface fluid injection, can trigger earthquakes (Walsh and Zoback 2015, and references therein). Increased pore pressures at depth can also occur naturally, for instance due to the pressure changes imposed by a waxing and waning ice sheet. A geological...
Content type: Publications -
2026:05 Thermally Induced Fracture Slip in Crystalline Rock: Experimental and Numerical Studies and Safety Implications for Geological Disposal of Nuclear Wastes
SSM perspective Background and objective High level radioactive waste, such as spent nuclear fuel, will continue to generate heat after the final disposal in an underground repository. The decay heat results in thermal expansion of the repository rock mass which can induce deformation of the fracture system. Near-field effects may involve thermally induced slip of a fracture crossing a...
Content type: Publications -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
2021:13 SSM’s external experts’ review of SKB’s safety evaluation SE-SFL
SSM perspective Background In Sweden long-lived low- and intermediate level radioactive waste is planned to be disposed in a repository (SFL) in the Swedish crystalline rock at a depth around 500 m. The waste contains mainly the long-lived wastes from the operation and decommissioning of the Swedish nuclear reactor plants, as well as the long-lived wastes from early research in the Swedish...
Content type: Publications -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Content type: Publications -
2023:02 Investigation of risk assessment for decommissioning waste to Fortum’s landfill at Norrtorp
Shulan Xu, Ryk Klos SSM English...
Content type: Publications -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications