Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement
Julie Flambard, F. Carrette, C. Monchy‐Leroy, Éric Andrieu, Lydia Laffont
Topics & Concepts
CorrosionCoolantPressurized water reactorMaterials scienceOxideDissolutionAlloyLayer (electronics)Boiler (water heating)SuperheaterMetallurgyComposite materialChemistryNuclear engineeringWaste managementThermodynamicsPhysical chemistryPhysicsEngineeringNuclear Materials and PropertiesHydrogen embrittlement and corrosion behaviors in metalsNuclear reactor physics and engineering