Rapporter

Din avgränsning ger 29 träffar.

• 2008:50 Study on Developments in Accident Investigation Methods: A Survey of the “State-of-the-Art”

  The objective of this project was to survey the main accident investigation methods that have been developed since the early or mid-1990s. The motivation was the increasing frequency of accidents that defy explanations in simple terms, for instance cause-effect chains or “human error”. Whereas...

  Innehållstyp: Publikationer

• SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1

  SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related...

  Innehållstyp: Publikationer

• 2008:06 Synthetic Aperture Focusing Technique in Ultrasonic Inspection of Coarse Grained Materials

  Experience from the ultrasonic inspection of nuclear power plants has shown that large focused transducers are relatively effective in suppressing grain (structure) noise. Operation of a large focused transducer can be thought of as an integration (coherent summation) of individual beams...

  Innehållstyp: Publikationer

• 2008:30 A model for fission gas release from mixed oxide nuclear fuel

  Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960's. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be...

  Innehållstyp: Publikationer

• 2007:26 Safety Culture Enhancement Project Final Report

  At the International Conference on Safety Culture in Nuclear Installations, organized by IAEA in 2002, one concluding remark was that the regulators should encourage a sincere interest in safety culture among licensees. In line with this SKI wanted to explore a proactive path to encourage the...

  Innehållstyp: Publikationer

• 2007:06 Probabilistic Safety Goals - Phase 1 -Status and Experiences in Sweden and Finland

  Based on a series of interviews and on literature reviews as well as on a limited interna- tional over-view, the project has described the history and current status of safety goals in Sweden and Finland. A number of issues were discussed more in detail, including the status of the safety goals...

  Innehållstyp: Publikationer

• 2007:39 Influence of Crack Morphology on Leak Before Break Margins

  The SKI regulation 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 that LBB prevails relies on a deterministic procedure for which a leakage...

  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...

  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...

  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...

  Innehållstyp: Publikationer