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Safety goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that...

Content type: Publications

2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

Cracked components are usually subjected to loads causing both primary and secondary stresses, e.g. welding components. Engineering assessment approaches, such as the ASME XI code and the R6 procedure, are commonly used to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these...

Content type: Publications

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2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods

2011:16 Modelling of ultrasonic testing of cracks in cladding

2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark

2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components

2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria

2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling

2010:35 Probabilistic Safety Goals for Nuclear Power Plants; Phases 2-4 / Final Report

2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

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