Din avgränsning ger 302 träffar.
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2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Innehållstyp: Publikationer -
2011:06 Reliability Data Handbook for Piping Components in Nordic Nuclear Power Plants – R Book, Phase 2
The Nordic PSA Group (NPSAG) has undertaken to develop a piping reliability parameter handbook for use in risk-informed applications that involve the consideration of structural integrity of piping systems. The scope of the handbook is to establish high quality reliability parameters that account for the Nordic and worldwide service experience with safety-related and non-safety-related piping...
Innehållstyp: Publikationer -
2011:16 Modelling of ultrasonic testing of cracks in cladding
During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark
Flow modelling using alternative assumptions regarding conceptual and parametric uncertainty in the spatial and structural relationships among fractures indicates elevated flow rates and groundwater velocities to deposition holes compared to SKB’s flow modelling results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural...
Innehållstyp: Publikationer -
2010:06 Upphandling inom kärnkraftsindustrin, kvalitet, säkerhet och beslutsfattande
Upphandling av tjänster eller annan inhyrd personal eller utrustning såsom byggnadsdelar, komponenter, system är att betrakta som en del av den kärntekniska verksamheten och ska därmed omfattas av ledningssystemet med tillhörande nödvändiga instruktioner (Strålsäkerhetsmyndighetens föreskrifter om säkerhet i kärntekniska anläggningar,...
Innehållstyp: Publikationer -
2010:07 Indicators of safety culture – selection and utilization of leading safety performance indicators
Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of...
Innehållstyp: Publikationer -
2010:37 Utvärdering av regler och normer för betongkonstruktioner i svenska kärnkraftsanläggningar
Syftet med projektet var att ta fram rekommendationer för tillämpning av regelverk för betongkonstruktioner i svenska kärnkraftsanläggningar genom att jämföra och utvärdera dels relevanta krav utgivna av europeiska och nordamerikanska myndigheter, och dels relevanta normer och standarder, riktlinjer eller liknande för betongkonstruktioner. Baserat på...
Innehållstyp: Publikationer -
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.
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer