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Filtered generated 30 hits.

• 2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models

  In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...

  Content type: Publications

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Content type: Publications

• 2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C

  SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...

  Content type: Publications

• 2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022

  The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...

  Content type: Publications

• 2025:02 INCLUDE: Including (local) stakeholder participation in the regulatory mission – a future challenge

  SSM perspective Background The primary focus of SSM’s communication with stakeholders in relation to the disposal of spent nuclear fuel and nuclear waste has for several years been on formal consultation processes surrounding the Swedish nuclear power industry’s research and development programme as well as SKB’s licence applications under the Nuclear Activities Act. Following licensing by...

  Content type: Publications

• 2012:11 Issues in the corrosion of copper in a Swedish high level nuclear waste repository

  The objective with this research project was to increase knowledge in the area of copper corrosion in the planned repository environment and obtain information on how copper corrosion evolves during the assessment period of 100 000 years. The equilibrium chemical composition of groundwater close to the canister as a function of temperature has been calculated by use of a thermodynamics code...

  Content type: Publications

• 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...

  Content type: Publications

• 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 stresses are present as well as a material were SCC can occur, SCC could potentially be a problem for the...

  Content type: Publications

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

  The Swedish Radiation Safety Authority reviews and assesses applications for geological 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 is important for the review and assessment for the long term safety of the spent nuclear...

  Content type: Publications

• 2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories

  Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that...

  Content type: Publications