Din avgränsning ger 740 träffar.
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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 -
96:71 Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken 1995-96
Revisionsavställningarna för vissa av reaktorerna blev längre än vad som var planerat detta år, till följd av utökade kontroller och reparationer. Detta har påverkat drifttillgängligheten. Antalet rapporterade händelser har legat på oförändrad nivå jämfört med tidigare år. Sex händelser har klassificerats...
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 -
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 -
1995:72 Kopparkorrosion i rent syrefritt vatten
Kopparkorrosion i rent vatten har studerats. Undersökningen är bl a föranledd av artiklar publicerade i Corrosion Science. I dessa artiklar presenterades resultat som visar att koppar kan korrodera i rent vatten i frånvaro av löst syrgas. Koppar oxideras i stället direkt av vattnet under bildning av vätgas. Kvartsprovrör innehållande rent vatten och...
Innehållstyp: Publikationer -
95:63 Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken 1994-95
Enligt proposition 1990/91:88 om energipolitiken skall regeringen varje år i budgetpropositionen redovisa drifts- och säkerhetsförhållanden vid de svenska kärnkraftreaktorerna. Regeringen har i regleringsbrevet uppdragit åt SK! att, i samarbete med Statens strålskyddsinstitut (SS!) årligen senast den 15 november till regeringen redovisa säkerhetsoch...
Innehållstyp: Publikationer -
2015:20 Guide for thyroid monitoring in the event of release of radioactive iodine in a nuclear emergency
This report aims to serve as a guide in the execution of a thyroid monitoring program during the intermediate phase of response to a nuclear emergency. Calibration factors for some instruments verified in the framework of the Nordic project THY- ROID (Nyander P. 2014) are listed here as an example. For different times after the intake, we present in this guide the measured values in net count...
Innehållstyp: Publikationer -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Innehållstyp: Publikationer -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Innehållstyp: Publikationer