Din avgränsning ger 302 träffar.
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2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
The study used the themes identified in an earlier study: definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...
Innehållstyp: Publikationer -
2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases
The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...
Innehållstyp: Publikationer -
2007:42 Regleringen av matarvattenflödet i en PWR - Med exempel från Ringhals 3
Rapporten ger en redovisning av kända och potentiella problem med matarvatten- regleringen i tryckvattenreaktorer, problem som i vissa fall förekommit tidigare internationellt. Vidare ges en detaljerad beskrivning av matarvattenregleringen vid Ringhals 3, som kan sägas vara representativ även för övriga svenska tryckvatten- reaktorer. Analysresultaten visar att R3:s...
Innehållstyp: Publikationer -
2006:06 Kontrollrumsfilosofi: Principer för kontrollrumsutformning och kontrollrumsarbete
Sedan flera år är begreppet kontrollrumsfilosofi etablerat inom svensk kärnkraftindustri. Syftet med en kontrollrumsfilosofi är att beskriva principerna för och de förutsättningar som personalen behöver för att kunna arbeta på ett säkert sätt. Kontrollrumsfilosofin ska ange interna krav och riktlinjer för utformning och ändringar...
Innehållstyp: Publikationer -
2020:11 Competency based assessments of Nuclear Power Plant controlroom operators
Experiences of development and first operational methodological and technical demonstrator application...
Innehållstyp: Publikationer -
2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...
Innehållstyp: Publikationer -
2020:07 Fibre Clogging in Nuclear Power Plants
SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...
Innehållstyp: Publikationer -
2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants
SSM perspective Background As the nuclear power plants are ageing, it is important to verify that every component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the event of an accident. There is a need within the nuclear industry for...
Innehållstyp: Publikationer -
2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling
SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...
Innehållstyp: Publikationer -
2021:05 Cladding tube rupture under LOCA: Data and models for rupture opening size
SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that is currently being studied in several research projects is the risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions were one is the possibility and size of a rupture of the fuel rod...
Innehållstyp: Publikationer