Filtered generated 217 hits.
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2009:16 Influence of Hardening Model on Weld Residual Stress Distribution
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 -
2008:30 A model for fission gas release from mixed oxide nuclear fuel
Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960´s. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...
Content type: Publications -
2007:23 On Safety Management, A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety
The authors present the theoretical framework. There they also discuss the pros of using the system perspective to build a useful frame of reference of safety management using non- nuclear organizations; this as a way to create models useful for the nuclear power industry but based on general understanding of the concept of safety management. The chosen organizations are used extensively to...
Content type: Publications -
2009:17 Effect of Welding Residual Stresses on Crack Opening Displacement and Crack-Tip Parameters
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. The fracture mechanical treatment of weld...
Content type: Publications -
SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook
SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need...
Content type: Publications -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Content type: Publications -
2015:04 DiD-PSA: Development of a Framework for Evaluation of the Defence-in-Depth with PSA
The project declares an interpretation of the definitions of Defence in Depth given by IAEA which outline a framework to meet PSA. For each level of defence and combinations of levels, methods to give estimates from a PSA perspective are presented and discussed. One important result is the discussion of the basic definitions and the basis for defence-in-depth, as defined by IAEA, leading to...
Content type: Publications -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Content type: Publications -
2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel
Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...
Content type: Publications -
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