Filtered generated 373 hits.
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2013:10 Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing
The purpose of this report is to describe programs and tools for assessment of accomplished and documented qualification with respect to ageing of electrical equipment and for development of complimentary ageing management programs. In addition to description of complete programs for management of ageing, tools for validation of the status with regard to ageing of installed (“old”) equipment...
Content type: Publications -
2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling
The report is a compilation report consisting of three papers. A safeguards approach for the planned encapsulation facility and the operating final repository is presented in paper 1. Special considerations concerning safeguards for the final disposal process have been discussed and incorporated into the approach. Paper 2 defines the spent fuel data that must be secured, for safeguards...
Content type: Publications -
2013:01 Validation of Weld Residual Stress Modeling in the NRC International Round Robin Study
Weld residual stresses (WRS) 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 on weld residual stresses is important to make proper decisions when cracks in weld joints are detected. During the latest years, there has been a strong development in both analytical procedures to...
Content type: Publications -
2012:66 Safety Leadership – the managerial art of balancing production pressure and safety
A substantial part of the project has been dedicated to investigating and characterizing ‘safety leadership’, set in the context of literature on safety leadership, safety culture and safety management, in order to build a solid theoretical basis. The authors have delved deeply into the theories and conceptualizations of leadership and analysed this area in order to further the understanding...
Content type: Publications -
2014:21 Effects of additives on uranium dioxide fuel behavior
This report will form a basis for the reviews that SSM does when the license holders applies for use of nuclear fuel with additives. The report is also intended as a reference to the models that Quantum Technologies AB has developed. The report and the models will be a valuable source of information for SSM and other parties when discussing the performance of doped fuel. Ali Massih SSM...
Content type: Publications -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Content type: Publications -
2010:01 Licensing of safety critical softwarefor nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors.
Content type: Publications -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Content type: Publications -
2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components
The Network for Evaluation of Structural Components (NESC) was started in 1993 and since then six different projects have been carried out. A seventh NESC-project is still in progress. The overall objective of these projects has been to study the reliability of the entire process of structural integrity assessment within an international framework. The network is coordinated by the European...
Content type: Publications -
2010:22 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16
This report constitutes Stage 16 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 15 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.
Content type: Publications