Din avgränsning ger 332 träffar.
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2017:07 Dimensionering av nukleära byggnadskonstruktioner (DNB)
Bakgrund Strålsäkerhetsmyndigheten (SSM) och de svenska tillståndshavarna har tidigare i ett samfinansierat forskningsprojekt tagit fram anvisningar för dimensionering av nukleära byggnadskonstruktioner, DNB. Rapporten som är baserad på Eurokoderna publicerades som SSM rapport 2014:06. DNB har sedan dess genomgått en generell uppdatering och publicerades...
Innehållstyp: Publikationer -
2017:22 Effect of weld repairs on residual stresses in nickel base dissimilar metal welds
Background The driving force for crack growth near welds in nuclear application piping may arise from weld residual stresses. Experience from nondestructive examination show that cracks in dissimilar metal welds are often found near weld repairs. The repair welding may affect the residual stresses through e.g. increased tensile stresses and increased plastic straining on the surfaces of the...
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 -
2021:07 Scenariourval i HFE-processen Arbetssätt och kriterier vid utvärdering av konstruktionens anpassning till människans förmåga
SSM perspektiv Bakgrund På en kärnteknisk anläggning genomförs under dess livstid så kallade anläggningsändringar i syfte att åtgärda identifierade brister, eller för att av andra skäl modernisera eller förbättra anläggningens konstruktion. Vid anläggningsändringar som påverkar arbetsuppgifter som har betydelse...
Innehållstyp: Publikationer