Filtered generated 209 hits.
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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...
Content type: Publications -
2011:20 A Guidebook for Evaluating Organizations in the Nuclear Industry – an example of safety culture evaluation
Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self- assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational...
Content type: Publications -
2013:29 Regulatory Approaches in Nuclear Power Supervision
The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...
Content type: Publications -
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...
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 -
2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Content type: Publications -
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...
Content type: Publications -
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...
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 -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...
Content type: Publications