|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Atomistic Simulation Study of the Effect of Hydride Morphology on the Ductility of Polycrystalline Zirconium
||Hadi Ghaffarian, Ye-eun Na, Dongchan Jang
|On-Site Speaker (Planned)
Zirconium alloys usually undergo degradation in their mechanical properties due to hydride formation during their service time. Although the zirconium hydride is considered a brittle phase, experimental observations indicate the occurrence of plasticity in the embedded hydride within the zirconium matrix, which involves the slip transmission across the Zr/Hydride interfaces. However, the corresponded mechanisms are still unclear due to experimental limitations. Hence, this study aims to look into the deformation mechanism of embedded hydride and clarifies the role of hydride morphology on the ductility of zirconium alloys using the Molecular Dynamics (MD) simulation method.
Based on this goal, we constructed nanocrystalline zirconium samples containing hydrides with different sizes, shapes, and orientations and subjected them to the tensile loading. We found that the ductility of the nanocrystalline zirconium samples is governed by the degree of slip transmission across the Zr/Hydride interface, whose transmission ability is altered by the hydride’s spatial configuration.
||Nuclear Materials, Modeling and Simulation, Computational Materials Science & Engineering