Din avgränsning ger 336 träffar.
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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 -
2007:13 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 -
2007:27 Kompetensöverföring på svenska kärnkraftverk i samband med pensionsavgångar
Rapporten visar att ett av Sveriges tre kärnkraftverk har ett program för kompetensöverföring. På de två som saknar program efterfrågas mer struktur inom området, även om man redan nu arbetar med mentorer eller handledare. Genomgående är upplevelsen av bristen på resurser för överrekrytering och tiden till att överföra.
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 -
2007:37 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 -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Innehållstyp: Publikationer -
2001:36 Kartläggning av strategiskakompetensbehov för kärntekniskverksamhet i nuläget och för framtiden
SKI skall, på uppdrag av regeringen, före utgången av år 2001 redovisa en uppdaterad strategi för sin framtida inriktning på forskningen och som ett led i detta arbete bedöma det framtida nationella kompetensbehovet och hur detta skall tillgodoses. ES-konsult har i detta sammanhang av SKI fått uppdraget att - genom en till industrin och säkerhetsmyndigheten...
Innehållstyp: Publikationer -
1997:40 Aging of Electrical Components in Nuclear Power Plants
The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...
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 -
96:40 Status and Use of PSA in Sweden
The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to...
Innehållstyp: Publikationer