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Din avgränsning ger 332 träffar.

• 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

• 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

• 2008:12 Independent Calculations for the SRCan Assessment

  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 spent nuclear...

  Innehållstyp: Publikationer

• 2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

  The aim of this applied study has been to demonstrate how a cost calculation is done in a systematic way. The framework of the project has been limited to older nuclear installations in Sweden. Furthermore, it may be envisaged that the process of making regular estimates of all the parameters is crucial in preparatory phases of decommissioning and dismantling processes. A secondary aim of the...

  Innehållstyp: Publikationer

• 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

  The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

  Innehållstyp: Publikationer

• 2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites

  An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...

  Innehållstyp: Publikationer

• 2007:02 Stakeholder involvement in Swedish nuclear waste management

  This report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden’s spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, in something more like a patchwork of different shapes and forms. Some of the...

  Innehållstyp: Publikationer

• 2007:32 Low pH Cements

  Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...

  Innehållstyp: Publikationer