Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water
Donghai Du, Kai Sun, Gary S. Was
Topics & Concepts
Materials scienceIrradiationGrain boundaryCorrosionUltimate tensile strengthMetallurgyAlloyStress (linguistics)Pressurized water reactorComposite materialMicrostructureNuclear engineeringNuclear physicsPhysicsPhilosophyLinguisticsEngineeringFusion materials and technologiesNuclear Materials and PropertiesHydrogen embrittlement and corrosion behaviors in metals