Rapporter

Din avgränsning ger 14 träffar.

• 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 recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...

  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 licensees in their safety culture work. SKI also had the ambition to gain more information on the MTO...

  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 in view of the fact that they are often exceeded, strategies for handling violations of safety...

  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 crack is postulated in certain sections of the pipe based on the leak detection capability of the...

  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

• 2007:22 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

• 2007:15 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

• 2007:04 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

• 2007:05 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

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

  The study carried out within the 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). This project covered the events reported in the IRS database with the incident date in the period of 1980- 01-01 – 2006-11-15. The events of highest...

  Innehållstyp: Publikationer