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Din avgränsning ger 80 träffar.

• 2010:34 The understanding of the formation of valleys and its implication on site characterization: Moredalen and Pukedalen, south-eastern Sweden

  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 ... viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. In south-eastern Sweden, there are a number of over-deepened narrow valleys, more than...

  Innehållstyp: Publikationer

• 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

  We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase ... phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material considered...

  Innehållstyp: Publikationer

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

  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 ... development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The objectives have been...

  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 ... 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 there is a satisfactory...

  Innehållstyp: Publikationer

• 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 mechanisms of buffer erosion...

  Innehållstyp: Publikationer

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

  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, which assessed the safety of a spent-fuel repository. A further safety report,...

  Innehållstyp: Publikationer

• 2016:21 The effect of a glaciation on East Central Sweden: case studies on present glaciers and analyses of landform data

  repositories for nuclear waste. When assessing the long term safety of the repositories it is important to consider possible future developments of climate and climate-related processes. Especially the next glaciation ... glaciation is important for the review and assessment for the long term safety of the spent nuclear fuel repository since the presence of a thick ice sheet influences the groundwater composition, rock stresses...

  Innehållstyp: Publikationer

• 2012:71 Identification of Brittle Deformation Zones and Weakness Zones

  In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority  (SSM) is conducting ... performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in bentonite...

  Innehållstyp: Publikationer

• 2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures

  codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical ... been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect of reinforcement was, in most cases, not...

  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 ... 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 non-sorbing tracers...

  Innehållstyp: Publikationer