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Study of the degradation mechanisms of zirconium alloy nuclear fuel claddings...
In nuclear plants, some accidental situations can result in air exposure of Pressurized Water Reactor (PWR) fuelassemblies: air ingress following a breach in the... -
Hydride Blister Formation and Induced Embrittlement Zircaloy-4 Cladding Tubes...
Our aim is to study the cladding fracture with mechanical tests more representative of RIA conditions, taking into account the hydrides blisters, representative strain... -
Characterization of fracture behavior of zirconium alloys for fuel rod claddi...
In order to guarantee the integrity of nuclear fuel rod cladding, it is necessary for EDF to characterize the ductility of cladding after a Loss of Coolant Accident... -
Thermomechanical processing of colonies of parallel lamellas in β-treated Zir...
Zircaloy-4 used for fuel cladding in nuclear plants is quenched from the β range and then extruded and rolled in the upper α range. At the start of this mechanical... -
Study of zircaloy-4 cladding air degradation at high temperature
Prix de la Meilleure Communication Européenne -
Modelling of Zircaloy-4 degradation in oxygen and nitrogen mixtures at high t...
Zircaloy-4 claddings provide the first containment of UO2 fuel in Pressurised Water Reactors. It has been demonstrated that the fuel assemblies cladding could be... -
Qualitative analysis of Zircaloy-4 cladding air degradation in O<sub>2</sub>-...
International audience -
Fracture of Zircaloy-4 cladding tubes with or without hydride blisters in uni...
International audience -
Corrosion mecanisms investigations of two alloys : zircaloy-4 et ZrNbO, under...
Pas de résumé en anglais
