Din avgränsning ger 748 träffar.
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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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2012:12 APRI-7 Accident Phenomena of Risk Importance. En lägesrapport om forskningen inom området svåra haverier under åren 2009-2011
Kunskap om de fenomen som kan uppträda vid svåra haverier i en kärnkraftanläggning är en viktig förutsättning för att kunna förutse anläggningens beteende, för att kunna utforma rutiner och instruktioner för haverihantering, för beredskapsplaneringen samt för att få god kvalitet på haverianalyser och riskstudier. Sedan...
Innehållstyp: Publikationer -
2011:24 Utredning och kartläggning av tillfällen då människan räddat och förbättrat en situation där automatiken inte räckt till eller fungerat fel
ÅF har genomfört en litteraturstudie och beskrivit en aktuell bild över rådande automations-filosofier och på vilket sätt människan påverkas av olika nivåer av automation. De har även kartlagt och beskrivit tre händelser inom kärnkraftsindustrin där människan ingripit och räddat eller förbättrat en situation där...
Innehållstyp: Publikationer -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...
Innehållstyp: Publikationer -
2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18
The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer