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  • 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
  • 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
  • 2007:02e Radiation Environment in Sweden, summary

    The radiation environment to which the population of Sweden is exposed is dominated by medical investigations and background radiation from the ground and building materials in our houses. That is the conclusion of the first general Swedish summary of environmental monitoring data and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of...

    Innehållstyp: Publikationer
  • 1999:13 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden

    Various mixed neutron-photon fields at workplaccs in the containment of pressurised water reactors and in the vicinity of transport containers with spent fuel elements were investigated with spectrometers and dosimeters.The spectral neutron fluences evaluated from measurements with multisphere systems were recommended to be used for the calculation of dosimetric reference values for...

    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