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Din avgränsning ger 81 träffar.

• 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

• 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

• 2009:30 A Review of Evidence for Corrosion of Copper by water

  The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...

  Innehållstyp: Publikationer

• 2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden

  A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...

  Innehållstyp: Publikationer

• 2009:21 The geological history of the Baltic Sea a review of the literature and investigation tools

  The bedrock in Sweden mainly comprises Proterozoic magmatic and metamorphic rocks older than a billion or one and a half billion years with few easily distinguished testimonies for the younger history. For construction of a geological repository for deposition of nuclear waste it is important to understand the late, brittle, geological events to be able to estimate its influence and...

  Innehållstyp: Publikationer

• 2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C

  Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile...

  Innehållstyp: Publikationer

• 2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility

  Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...

  Innehållstyp: Publikationer

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

  The design 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 loads have 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...

  Innehållstyp: Publikationer

• 2013:32 Upparbetning av utbränt kärnbränsle - En studie med fokus på exportkontroll

  Rapporten beskriver principerna för upparbetning samt egenskaperna hos utbränt kärnbränsle där sammansättningen hos det i reaktorn bildade plutoniumet är av avgörande betydelse för kärnvapenframställning till skillnad från civil upparbetning. Rapporten går igenom ett antal upparbetningsmetoder, både äldre metoder samt nya,...

  Innehållstyp: Publikationer