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  • 2001:21 Work in Support of Biosphere Assessments for Solid Radioactive Waste Disposal. 1. Performance Assessments, Requirements and Methodology; Criteria for Radiological Environmental Protection

    The first part of this report is intended to assess how the recent Swedish regulatory developments and resulting criteria impose requirements on what should be included in a performance assessment (PA) for the SFR low and medium level waste repository and for a potential deep repository for high level waste. The second part of the report has been prepared by QuantiSci as an input to the...

    Content type: Publications
  • 1986:12 Chernobyl - its impact on Sweden

    In case of a radiological emergency in Sweden, the Swedish National Institute of Radiation Protection (SSI) has the responsibility of organ1z1ng a special task force with experts both from SSI and from other authorities. Reports of increased radiation l evels reached SSI around 10 am on April 28, 1986, and the task force convened at 1030 am. A large number of measurements were made all over...

    Content type: Publications
  • 1994:08 The content and environmentalimpact from the waste depositoryin Sillamae

    The studies of the waste depository in Sillamae, Estonia, shows that the content as well as the wall material is typical tailings from chemical enrichment of uranium ore. The environmental impact from radioactive substances as well as heavy metals has been estimated. Results show the major radiological impact to the population in the Sillamae town is the exposure to radon and its daughter...

    Content type: Publications
  • 2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures

    The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...

    Content type: Publications
  • 2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C

    The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...

    Content type: Publications
  • 2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?

    The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...

    Content type: Publications
  • 2009:28 Biogeochemistry of Redox at Repository Depth and Implications for the Canister

    The present groundwater chemical conditions at the candidate sites for a spent nuclear fuel repository in Sweden (the Forsmark and Laxemar sites) and processes affecting its future evolution comprise essential conditions for the evaluation of barrier performance and long-term safety. This report reviews available chemical sampling information from the site investigations at the candidate...

    Content type: Publications
  • 2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark

    SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...

    Content type: Publications
  • 2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review

    Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...

    Content type: Publications
  • 2010:31 Buffer erosion: An overview of concepts and potential safety consequences

    In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...

    Content type: Publications