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  • 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
  • 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
  • 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
  • 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