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Filtered generated 21 hits.

• 2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants

  This report has been prepared by order of the Swedish government in accordance with the “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. The Swedish Radiation Safety Authority has through its supervision ensured a comprehensive basis for this overall assessment of radiation safety. The overall conclusion is that the radiation safety,...

  Content type: Publications

• 2009:07 Dependency Analysis Guidance Nordic/German Working Group on Common Cause Failure analysis

  The Regulatory Code SSMFS 2008:1 of Swedish Radiation Safety Authority (SSM) includes requirements regarding the performance of probabilistic safety assessments (PSA), as well as PSA activities in general. Therefore, the follow-up of these activities is part of the inspection tasks of SSM. According to the SSMFS 2008:1, the safety analyses shall be based on a systematic identification and...

  Content type: Publications

• 2009:05 Survey on requirements for independent reviews and inspections of electrical and I&C equipment

  This survey is a first step to support the work to develop the Swedish regulations in the area of independent review and inspection in the process supporting implementation of electrical equipment in nuclear power plants. The report consists of a summary of different regulations in the area and also an analysis of the differences between the electrical and mechanical field especially in the...

  Content type: Publications

• 2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials

  SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...

  Content type: Publications

• 2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden

  A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...

  Content type: Publications

• 2009:21 The geological history of the Baltic Sea a review of the literature and investigation tools

  The bedrock in Sweden mainly comprises Proterozoic magmatic and metamorphic rocks older than a billion or one and a half billion years with few easily distinguished testimonies for the younger history. For construction of a geological repository for deposition of nuclear waste it is important to understand the late, brittle, geological events to be able to estimate its influence and...

  Content type: Publications

• 2009:08 Shear-induced Fracture Slip and Permeability Change - Implications for Long-term Performance of a Deep Geological Repository

  Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the...

  Content type: Publications

• 2009:30 A Review of Evidence for Corrosion of Copper by water

  The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...

  Content type: Publications

• 2009:32 On Younger Stakeholders and Decommissioning of Nuclear Facilities

  An appropriate balance in this regard must be based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data...

  Content type: Publications

• 2009:31 A Review of the Decommissioning Costs of the Ranstad Site

  The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary “bench-marking” studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been...

  Content type: Publications