Filtered generated 29 hits.
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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 -
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 -
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...
Content type: Publications -
International radiation safety course in Stockholm gives participants practical knowledge
With radiation protection experts from all over the world and a focus on practical exercises and case studies, International Radiological Protection School (IRPS) gives professionals from over 20 different countries the opportunity for increased understanding of international radiation protection issues.
Content type: News -
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 -
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 -
The international radiation protection school in Stockholm attracts participants from over 20 countries
For five days, at Stockholm University, international early and mid-career radiation protection experts gather to develop their knowledge in radiation protection. The course alternates between theory and practice and provides in-depth knowledge and understanding on the structure and application of the international system for radiation protection.
Content type: News -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
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 -
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