Din avgränsning ger 401 träffar.
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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...
Innehållstyp: Publikationer -
2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program
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...
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.
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