Din avgränsning ger 302 träffar.
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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 -
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