Threshold stress of hydride reorientation in zirconium alloy nuclear fuel cladding tubes: A theoretical determination
Wen Qin, J.L. Liang, Z.Q. Cheng, Minghua Shi, Di Gu, T.L. Li, Weiling Zhu, Jerzy A. Szpunar
Topics & Concepts
HydrideCladding (metalworking)Zirconium alloyZirconium hydrideMaterials scienceZirconiumGrain boundaryStress (linguistics)MetallurgyHydrogenCylinder stressAnisotropyAlloyNuclear fuelComposite materialChemistryMicrostructureUltimate tensile strengthNuclear chemistryPhilosophyOrganic chemistryPhysicsLinguisticsQuantum mechanicsMetalNuclear Materials and PropertiesFusion materials and technologiesNuclear reactor physics and engineering