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  • 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
  • 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
  • 2013:01 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
  • 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...

    Innehållstyp: Publikationer
  • 2015:11 Investigation of the Distribution of Phosphorus in Copper

    Two copper alloys containing different amounts of phosphorus, 6 and 80 wtppm, respectively, have been investigated. The matrix of both alloys was analysed using atom probe tomography (APT). The matrix P concentration in the 80 wtppm P mate- rial was about the same as the bulk concentration and it was therefore concluded that the majority of the P atoms resides in the matrix. Grain boundaries...

    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
  • 2014:56 Seismic design and analysis of safety-related nuclear structures in Sweden

    The report presents the historical development of the seismic design for the U.S., France and Sweden with special focus on issues related to severe earthquakes beyond the design basis as well as important aspects concerning the design basis ground motions for the Swedish nuclear facilities. The report provides recommendations on a revised model for seismic hazard assessments, on minimum...

    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