Din avgränsning ger 151 träffar.
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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.
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
Innehållstyp: Publikationer -
2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment
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
Innehållstyp: Publikationer -
2020:06 Bestrålningsinducerad spänningskorrosion (IASCC) i BWR- och PWR-miljö
En sammanställning av kunskapsläget med fokus på erfarenheter av studier genomförda i Sverige
Innehållstyp: Publikationer -
2020:05 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the nuclear reactors Ringhals 1 and Ringhals 2 in Sweden
Innehållstyp: Publikationer -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow
Innehållstyp: Publikationer -
2019:29 Myndighetsstöd: Artificiell Intelligens – tillämpning inom kärnkraften
SSM perspektiv Bakgrund Området artificiell intelligens (AI) genomgår en omfattande utveckling och stora satsningar görs inom FoU på olika håll runt om i världen. Vinnova fick under 2017 i uppdrag av regeringen att genomföra en kartläggning och analys av hur
Innehållstyp: Publikationer -
2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study
SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high
Innehållstyp: Publikationer -
2019:25 Maskulinitet, risk och säkerhet vid ett svenskt kärnkraftverk
SSM perspektiv Bakgrund Likt anställda vid ett järnverk, ett pappersbruk eller en oljeplattform omges även personalen vid ett kärnkraftverk av olika slags risker som hanteras genom ett mer eller mindre lyckosamt säkerhetsarbete. Kärnkraften är en högriskbransch
Innehållstyp: Publikationer