Litcius/Paper detail

Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment

Weisong Wu, Guang Ran, Yipeng Li, Shuo Cong, Chao Ye, Ruiqian Zhang, Yongduo Sun

2020Corrosion Science51 citationsDOI

Topics & Concepts

CorrosionMaterials scienceAlloyOxideMetallurgyLayer (electronics)IrradiationSpinelPressurized water reactorComposite materialNuclear engineeringNuclear physicsEngineeringPhysicsNuclear Materials and PropertiesHigh-Temperature Coating BehaviorsHydrogen embrittlement and corrosion behaviors in metals
Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment | Litcius