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  • 2010:08 Development of COLLAGE 3

    The issue of colloid-facilitated radionuclide transport (CFRT) was last addressed by the Swedish nuclear regulators (SKI at that time, now integrated into SSM) in 2001 – 2002. SKI had commissioned the Collage code with subsequent development as Collage 2. This code was employed to investigate the potential role for colloids to have been involved in the transport of radionuclides at the Nevada...

    Innehållstyp: Publikationer
  • 2010:17 Quality Assurance Review of SKB’s Copper Corrosion Experiments

    SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...

    Innehållstyp: Publikationer
  • 2010:23 On Decommissioning Costs of the Ranstad Site

    A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister

    The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...

    Innehållstyp: Publikationer
  • 2007:08 DECOVALEX-THMC - Task B

    This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...

    Innehållstyp: Publikationer
  • 2007:11 Review of Quality Assurance in SKBs Repository Research Experiments

    SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...

    Innehållstyp: Publikationer
  • 2007:30 Modelling the Interaction of Low pH Cements and Bentonite

    Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...

    Innehållstyp: Publikationer