Rapporter

Din avgränsning ger 55 träffar.

• 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

• 2007:15 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

• 2007:35 Urananrikning med laser och plasmaseparation - en analys med fokus på exportkontroll

  Den nu resulterande rapporten berör kortfattat några generella principer för laseranrikning, både separation av atomärt uran – AVLIS - och separation av uran i molekylär form – MLIS. Vidare berörs mycket översiktligt några andra metoder inklusive plasmaseparation. Dessutom nämns vilken utrustning som kan komma ifråga, indikatorer på laseranrikning,...

  Innehållstyp: Publikationer

• 2007:13 Elektrokemiska aspekter på korrosion i svenska reaktorinneslutningar

  Samtliga svenska reaktorinneslutningar är konstruerade av spännarmerad betong. Ingjutningsgods i betong skyddas normalt mot korrosion genom att porvattnet i betongen är starkt alkaliskt. Denna miljö medför att stål passiveras. Under speciella omständigheter kan korrosion ändå uppstå. Viss uppföljning av korrosionsbilden i reaktorinneslutningarna...

  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

• 2007:24 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

• 2007:25 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

• 2007:17 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