Filtered generated 80 hits.
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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 -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications -
2024:01 Stress field modelling of the Forsmark lens – Correlation of stress measurements with stress field simulations
SSM perspective Background and objective Understanding the in-situ stress field in the Forsmark tectonic lens will lay the fundamental basis to characterise the prevailing mechanical and hydraulic behaviour of the rock mass. Only with a good understanding of the geomechanical setting including the stress field an analysis of future rock mass behaviour under the evolution of conditions in a...
Content type: Publications -
2008:10 User’s manual for Ecolego Toolbox and the Discretization Block
The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...
Content type: Publications -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Content type: Publications -
2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment
With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...
Content type: Publications -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
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