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  • 2015:25 Design Guide for Nuclear Civil Structures (DNB)

    The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...

    Innehållstyp: Publikationer
  • 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

    Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 2010:24 On Cost Estimate for Decommissioning of one Isotope Central

    The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...

    Innehållstyp: Publikationer
  • 2009:19 Review of SKB’s Quality Assurance Programme

    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
  • 2010:05 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...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method

    The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...

    Innehållstyp: Publikationer
  • 2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption

    For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...

    Innehållstyp: Publikationer
  • 2010:33 Lineament interpretation Short review and methodology

    This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site that may have potential for hosting a...

    Innehållstyp: Publikationer