Publikationer

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  • 2007:23 On Safety Management, A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    The authors present the theoretical framework. There they also discuss the pros of using the system perspective to build a useful frame of reference of safety management using non- nuclear organizations; this as a way to create models useful for the nuclear power industry but based on general understanding of the concept of safety management. The chosen organizations are used extensively to...

    Innehållstyp: Publikationer
  • 2007:33 Analys av mänsklig tillförlitlighet HRA-begreppets tillämpbarhet vid revisionsavställning

    Analyser av mänsklig tillförlitlighet, Human Reliability Analysis (HRA) har använts under en längre tid i kärnkraftverkens probabilistiska säkerhetsanalyser. SKI har nyligen genomfört en utredning om befintliga metoder inom området HRA (litteraturstudie) och hur dessa metoder används av tillståndshavarna för de svenska kärnkraftverken...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR

    An input model has been prepared for the Oskarshamn 3 rector. Demonstrations calculations, at current nominal operating conditions in Oskarshamn 3 for 3300 MW thermal power, were performed for three cases: (1) initial, steady-state conditions, (2) total loss of AC power and (3) large steam line LOCA. The results are presented in the report. 200 Lars Nilsson SKI English An input model has been...

    Innehållstyp: Publikationer
  • 2007:02 Strålmiljön i Sverige

    Rapporten beskriver, och redovisar resultat från, den strålmiljöövervakning som bedrivits i Sverige sedan 1950-talet. Genomsnittliga doser till befolkningen och till speciella befolkningsgrupper redovisas också. En stor del av övervakningen har rört nedfallet och spridningen i ekosystemen av radioaktiva ämnen från de atmosfäriska kärnvapenproven...

    Innehållstyp: Publikationer
  • 2007:45 Icke-spridning och kärnämneskontroll

    Det kompendium som nu föreligger kommer att användas både inom och utom landet som kursmaterial vid utbildningar. Det är delvis ett resultat av ESARDA:s (European Safeguards Research and Development Association) arbetsgrupp TKM (Training and knowledge management) som årligen utbildar studenter från hela Europa. Avsikten är även att använda det i samband...

    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
  • 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
  • 2007:19 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 work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...

    Innehållstyp: Publikationer