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  • 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
  • 2011:13 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
  • 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...

    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
  • 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

    Ali R. Massih, Lars Olof Jernkvist SSM English...

    Innehållstyp: Publikationer
  • 2015:25 Design Guide for Nuclear Civil Structures (DNB)

    The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...

    Innehållstyp: Publikationer
  • 2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen

    One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...

    Innehållstyp: Publikationer
  • 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

    Innehållstyp: Publikationer
  • 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

    Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

    Innehållstyp: Publikationer
  • 2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS

    Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...

    Innehållstyp: Publikationer