Filtered generated 21 hits.
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2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
Content type: Publications -
2009:05 Survey on requirements for independent reviews and inspections of electrical and I&C equipment
This survey is a first step to support the work to develop the Swedish regulations in the area of independent review and inspection in the process supporting implementation of electrical equipment in nuclear power plants. The report consists of a summary of different regulations in the area and also an analysis of the differences between the electrical and mechanical field especially in the...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants
This report has been prepared by order of the Swedish government in accordance with the “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. The Swedish Radiation Safety Authority has through its supervision ensured a comprehensive basis for this overall assessment of radiation safety. The overall conclusion is that the radiation safety,...
Content type: Publications -
2009:01 Decommissioning of the Nuclear Reactors R2 and R2-0 at Studsvik, Sweden – General Data as called for under Article 37 of the Euratom Treaty
The report describes the plans for decommissioning of the nuclear research and material test reactors R2 and R2-0, situated at the Studsvik site in Sweden. The purpose of the document is to serve as information for the European Commission, and to fulfil the requirements of Article 37 of the Euratom Treaty. According to Article 37, each Member State shall provide the Commission with such...
Content type: Publications -
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...
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 -
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