Filtered generated 217 hits.
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2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...
Content type: Publications -
2010:45 Evaluation of models for cyclic plastic deformation – A literature study
Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...
Content type: Publications -
2007:22 Safety Management An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts
A systems perspective has been applied on safety management that will be the foundation for the frame of reference the authors intend to build during the three-year long project. The case studies are presented and form illustrations of both high quality safety management and weaknesses of the safety management and take a look at information feedback about the risks of the systems. An...
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 -
Research on nuclear materials and waste to be strengthened with new partnerships within the EU
Two new major partnerships for research on materials in nuclear energy and nuclear waste management have been launched this autumn. The Swedish Radiation Safety Authority (SSM) actively participates in the partnerships and also contributes with research funds to projects that are granted funding. A total of three partnerships are now ongoing, distributing altogether 70 million euros over a...
Content type: News -
2021:10 Establishment and use of attention values in environmental fatigue assessments
SSM perspective Background As Swedish NPPs reach their original technical design life, re-assessment of the fatigue life of structural components is needed for safe long term operation (LTO). In these re-assessments one must consider that new knowledge has shown that environmental effects on fatigue life must be considered. One common method to verify the fatigue life of structural components...
Content type: Publications -
2021:20 Effects of additives on UO2 fuel behavior: expanded edition
SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the development of nuclear fuel closely. Fuel with additives like chromia and gadolinia is used in Swedish reactors and fuel with even better thermal and mechanical properties is under development. This project is an in-depth study of data and models regarding the impact of additives on the properties of uranium...
Content type: Publications -
2017:34 Human capability to cope with unexpected events är publicerad
Background In the light of the Fukushima accident, it stood clear that the challenge of the unexpected is of great importance to both regulators and licensees. For SSM, as for many other national regulators, there was a selfevident need to learn more about the capabilities and actions of people when the unexpected arises and conditions are potentially extreme. A task group was set up within...
Content type: Publications -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Content type: Publications -
2017:25 Evaluation of weld fatigue reduction in austenitic stainless steel pipe components
Background The performed investigation is a continuation of the work performed in SSM 2015:38 where fatigue tests were performed on pressurized welded austenitic stainless steel piping components. The specimens were subjected to a realistic variable amplitude loading with mainly reversed bending deformation and particular focus on high cycle fatigue. The previous fatigue results were quite...
Content type: Publications