Din avgränsning ger 565 träffar.
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2008:54 Vägledning för insatsplanering i kärntekniska anläggningar
Vägledningsdokumentet ger en processbeskrivning för att utforma systemet för insatsplanering, däremot inte att skapa färdiga instruktioner och layouter. Ett stöd för att planera insatsen är information om olika typbränder. Typbrand är en enkel beskrivning av hur en viss typ av brand kan utvecklas och dess eventuella risker samt val av släckmedel...
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 activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
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 -
2007:04 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 -
2007:15 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 -
2001:10 Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken 2000
Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken är gott. Säkerheten och strålskyddet upprätthölls under 2000 på en tillfredsställande nivå i förhållande till de säkerhets- och strålskyddskrav som ställs, vilka är jämförbara med de krav som är allmänt accepterade i jämförbara...
Innehållstyp: Publikationer -
2000:15 Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken 1999
Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken under tillsyn av Statens kärnkraftinspektion (SKI) och Statens strålskyddsinstitut (SSI) är gott. Säkerheten och strålskyddet upprätthölls under 1999 på en tillfredsställande nivå i förhållande till de säkerhets- och strålskyddskrav som ställs...
Innehållstyp: Publikationer -
99:10 Verification and Validation of HumanFactors Issues in Control RoomDesign and Upgrades
Systems, facilities and equipment are periodically updated during a power plant's lifetime. This has human factors implications, especially if the central control room is involved. Human factors work may therefore be required. There is an extensive literature on human factors itself, but not so much on how it is verified and validated. Therefore, HRP and the Swedish Nuclear Power Inspectorate...
Innehållstyp: Publikationer -
1997:12 Study of International Published Experiences in Joining Copper and Copper-alloys
This study has revealed a number of joining processes to be used when manufacturing copper-canisters for the final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified i.e, it shall be demonstrated whether the procedure is capable of fulfilling...
Innehållstyp: Publikationer -
1995:60 Reliability of Piping System Components -Volume 3: A Bibliography of Technical Papers and Reports Related to Piping Reliability
Reflecting on older analysis practices, passive components failures seldom receive explicit treatment in PSA. to expand the usefulness of PSA and to raise the realism in plant and system models the Swedish Nuclear power Inspectorate has undertaken a multi-year research project to establish a comprehensive passive components database, validate failure rate parameter estimates and model...
Innehållstyp: Publikationer