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  • 2007:31e Safety and Radiation Protection at Swedish Nuclear Power Plants 2006

    Safety related problems in the electric systems of the Forsmark 1 reactor were the dominant event in Swedish nuclear power plants in 2006. The incident has had a significant impact on our attitude towards ... reliability of how safety systems function both in Sweden and abroad. In connection with SKI’s review of the incident it was found that the company’s management system was not implemented correctly in conjunction...

    Innehållstyp: Publikationer
  • 2007:43 ProLBB - A Probabilistic Approach to LeakBefore Break Demonstration

    698 84 00 TELEFAX +46 (0)8 661 90 86 E-POST/E-MAIL ski@ski.se WEBBPLATS/WEB SITE www.ski.se ProLBB - A Probabilistic Approach to Leak Before Break Demonstration Peter Dillström Weilin Zang November 2007 ... SKIFS 2004:2 allows for the use of Leak Before Break (LBB) as one way to provide assurance that adequate protection exists against the local dynamic consequences of a pipe break. The way to demonstrate...

    Innehållstyp: Dokument
  • 2007:37 Identification of Common Cause Initiating Events Using the NEA IRS Database

    framework of this project is a continuation of work conducted for SKI in 1998 on the identification of Common Cause Initiators based on operational events documented in the NEA Incident Reporting System (IRS) ... events reported in the IRS database with the incident date in the period of 1980- 01-01 – 2006-11-15. The events of highest concern in nuclear power plants today are the dependent events, where a single event...

    Innehållstyp: Publikationer
  • 2007:31e Safety and Radiation Protection at Swedish Nuclear Power Plants 2006

    .......................... 14 Requirements for more extensive ageing management programmes at nuclear facilities ... 14 Overall development of degradation and the influencing factors .............. ... .......................... 15 Mechanical components which are part of the barriers and defence in depth ................. 15 Reactor containment.....................................................

    Innehållstyp: Dokument
  • 2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The ... process of estimating the parameters of decommissioning is one of the main issues in preparatory phases of decommissioning processes. The main aim of the presented project has been to present a comprehensive...

    Innehållstyp: Publikationer
  • 2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment

    (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered ... Engineered Barrier System (EBS) and spent fuel. This workshop concerns the assessment of the spent fuel performance and near-field radionuclide retardation mechanisms in the engineered barriers. This will...

    Innehållstyp: Publikationer
  • 2007:10 DECOVALEX-THMC - Task D

    Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project ... coupled processes in geologic formations in support of the performance assessment for underground storage of radioactive waste. Three multi-year project stages of DECOVALEX have been completed in the past decade...

    Innehållstyp: Publikationer
  • 2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister

    The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long ... long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration tests at...

    Innehållstyp: Publikationer
  • 2007:02 Stakeholder involvement in Swedish nuclear waste management

    Research SKI Report 2007:02 ISSN 1104-1374 ISRN SKI-R-07/02-SE STAKEHOLDER INVOLVEMENT IN SWEDISH NUCLEAR WASTE MANAGEMENT Mark Elam Göran Sundqvist September 2006 SKI-perspective Background ... management has been produced as part of a cross national research project: CARL – A Social Science Research Project into the Effects of Stakeholder Involvement on Decision-Making in Radioactive Waste Management...

    Innehållstyp: Dokument
  • 2007:14 Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions

    Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions Ali R. Massih February 2007 SKI Perspective Background and purpose of the project ... the behaviour of nuclear fuel during loss of coolant accidents (LOCA) has been studied to investigate the failure behaviour at high burnup and for modern fuel cladding. The results of recent experimental...

    Innehållstyp: Dokument