Publikationer

Din avgränsning ger 55 träffar.

• 2007:24 Safety Management in Non-Nuclear Contexts Examples from Swedish Railway Regulatory and Company Perspectives

  The authors describe important features of safety management and the results are modelled according to the systems perspective developed. These are definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reporting, and...

  Innehållstyp: Publikationer

• 2007:42 Regleringen av matarvattenflödet i en PWR - Med exempel från Ringhals 3

  Rapporten ger en redovisning av kända och potentiella problem med matarvatten- regleringen i tryckvattenreaktorer, problem som i vissa fall förekommit tidigare internationellt. Vidare ges en detaljerad beskrivning av matarvattenregleringen vid Ringhals 3, som kan sägas vara representativ även för övriga svenska tryckvatten- reaktorer. Analysresultaten visar att R3:s...

  Innehållstyp: Publikationer

• 2007:04 Link Between RI-ISI and Inspection Qualification: Relationship between Defect Detection Rate and Margin of Detection

  A relationship has been established between defect detection ratio and margin of detection based on blind trails. The results are based on a rather small amount of data produced by personnel from one inspection laboratory but give us indications of how signal to noise ratio is possible to relate to the probability of detection (POD) used in RI-ISI models. The relationship need to be developed...

  Innehållstyp: Publikationer

• 2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

  The study used the themes identified in an earlier study: definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...

  Innehållstyp: Publikationer

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

  This project has contributed to the research goal of giving a basis for SKIs supervision by means of evaluating experimental data and modelling the nuclear fuel cladding during a design base accident. The project has also contributed to the research goal to develop the competence about licensing of fuel at high burnup, which is an important safety issue. The results are useful as such, but...

  Innehållstyp: Publikationer

• 2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases

  The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...

  Innehållstyp: Publikationer

• 2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod

  The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...

  Innehållstyp: Publikationer

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

  SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (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 Barrier System (EBS) and spent fuel. This workshop...

  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 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...

  Innehållstyp: Publikationer

• 2007:08 DECOVALEX-THMC - Task B

  This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...

  Innehållstyp: Publikationer