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  • 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...

    Content type: Publications
  • 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

    Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...

    Content type: Publications
  • 2007:22 Safety Management An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

    A systems perspective has been applied on safety management that will be the foundation for the frame of reference the authors intend to build during the three-year long project. The case studies are presented and form illustrations of both high quality safety management and weaknesses of the safety management and take a look at information feedback about the risks of the systems. An...

    Content type: Publications
  • 2006:25 Modelling of ultrasonic nondestructive testing of cracks in claddings

    Anders Boström, Theo Zagbai SKI English...

    Content type: Publications
  • 2014:43 Technical Note, Workshop on general corrosion of copper

    This report describes the outcome of the workshop organized by SSM on general corrosion of copper that was held in Stockholm on the 26-27th of August, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...

    Content type: Publications
  • 2015:47 GEMA-Site 1: Model description and example application

    Background In 2011 the Swedish Nuclear Fuel and Waste Management Company (SKB) submitted an assessment of the long-term safety of a KBS-3 geological disposal facility for spent nuclear fuel in Forsmark, Sweden. This assessment, the SR-Site project, supports the licence application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site...

    Content type: Publications
  • 2015:06 Technical Note, Feasibility of Backfilling Deposition Tunnels

    SKB has been conducting an appropriate scientific and technical programme of research and development work to investigate the many processes that may affect the choice of backfill materials, the practicali- ties of backfill emplacement, and the properties of the emplaced backfill that may affect long-term radiological safety. On the basis of this re- search and development work SKB has outlined...

    Content type: Publications
  • 2014:39 Technical Note, “Wormhole” and Multiple Loss of Buffer Safety Function Scenarios

    This Technical Notes reviewed the issues that may cause canister corrosion other than the cases evaluated by SKB, which may belong to “What-if” canister corrosion scenarios. This Notes, in particular, addressed two potential canister corrosion scenarios: “wormhole” formation and loss of multiple buffer safety functions. The “wormhole” scenario was hypothesized during the SSM Workshop on...

    Content type: Publications
  • 2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase

    The review assignment SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: 1. Adequacy of the methods adopted by SKB for conducting sensitivity analyses 2. Approach for use of conservative and best-estimate parameter values 3. Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity...

    Content type: Publications
  • 2015:01 Technical Note, Rock Mechanics - Thermal properties and thermal modelling of the rock in a repository of spent nuclear fuel at Forsmark – Main Review Phase

    In preparation for the review of SKB's license application for a disposal of spent nuclear fuel, SSM has conducted a series of modelling studies related to the design, construction and long-term safety of a repository at Forsmark. Several of the presented modelling works are related to the thermal evolution of the repository with time. This report extracts the results from independent SSM...

    Content type: Publications