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  • 2010:47 Utveckling av programpaket för analys av termisk utmattning

    I ett tidigare NESC-projekt (Network for Evaluating Structural Components – Thermal Fatigue) togs fram en Europeisk procedur för hantering av termisk utmattning. Den tidigare myndigheten Statens kärnkraftinspektion (SKI) var en av projektets finansiärer. Proceduren innehåller bl.a. utvärdering av en modell för analys av högcykelutmattning vid turbulent termisk...

    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
  • 2018:27 ESHM13 – En ny PSHA-modell för Europa betraktad ur ett svenskt perspektiv

    Sammanfattning Den seismiska verieringen av de svenska kärntekniska anläggningarna görs idag med användning av markresponsspektra enligt SKI TR 92:3. Inom ramen för ett stort gemensamt europeiskt forskningsprojekt (SHARE/ESHM13) utvecklades den första enhetliga seismiska riskmodellen för hela Europa med seismiska riskkurvor och markresponsspektra för olika...

    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
  • 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
  • 1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy

    A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...

    Innehållstyp: Publikationer
  • 98:35 Nuclear Fuel Assembly Assessment Project and Image Categorization

    C. S. Lindsey (1), T. Lindblad (1), K. Waldemark (1), L. Hildningsson (2). (1) Royal Institute of Technology, Stockholm, Sweden. (2) Swedish Nuclear Power Inspectorate, Stockholm, Sweden. July 1998 SKI English...

    Innehållstyp: Publikationer
  • 2008:10 User’s manual for Ecolego Toolbox and the Discretization Block

    The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...

    Innehållstyp: Publikationer
  • Tubbrott i en tryckvattenreaktor

    Svenska tryckvattenreaktorer har tre ånggeneratorer som innehåller tusentals tuber. Tuberna är en säkerhetsbarriär mellan kärnkraftverkets primär- och sekundärkrets.Om en tub går av måste reaktorn stoppas och den skadade ånggeneratorn isoleras. Faktabladet beskriver vad som händer vid ett tubbrott i en tryckvattenreaktor.

    Innehållstyp: Publikationer