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Filtered generated 24 hits.

• 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

• 2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

  In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...

  Content type: Publications

• 2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review

  Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...

  Content type: Publications

• 2008:08 Review of SKB:s Work on Coupled THM Processes Within SR-Can External review contribution in support of SKI:s and SSI:s

  The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...

  Content type: Publications

• 2008:48E Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co´s (SKB) RD&D Programme 2007

  The review of the RD&D Programmes (Research, Development, Demonstration) prepared by the Swedish Nuclear Fuel and Waste Management Co (SKB) is a recurrent task that the Swedish Nuclear Power Inspectorate (SKI) must carry out as a regulatory authority with the support of reviewing bodies of which the most important is the Swedish Radiation Protection Authority (SSI). The review statement for...

  Content type: Publications

• 2008:47 Selected Models for Key Processes in a Nuclear Waste Repository

  The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...

  Content type: Publications

• SSMFS 2008:1 The Swedish Radiation Safety Authority’s Regulations concerning Safety in Nuclear Facilities

  SSMFS 2010:3 is only available in Swedish. The latest consolidated version of the regulation with amendments made up to and including SSMFS 2018:12 is only available in Swedish. SSM English SSMFS 2010:3 is only available in Swedish. The latest consolidated version of the regulation with amendments made up to and including SSMFS 2018:12 is only available in Swedish.

  Content type: Publications

• 2008:29e Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

  The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In...

  Content type: Publications