|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Nanoindentation creep of metallic uranium alloys
||Tzu-Yi Chang, Gavin Vandenbroeder, David M Frazer, Yushu Dewen, Tianyi Chen
|On-Site Speaker (Planned)
Understanding the creep on nuclear fuel and structural materials is essential for safe reactor operation. The challenges with conventional creep measurements are the long time-scales and high radiation levels from the large samples. Nanoindentation creep measurements hold promise as they have been shown to measure similar values to macro-scale creep testing at significantly reduced times. However, work still needs to be done as conventional macroscale creep is usually performed in a uniaxial fashion as compared to the rather complicated stress state under the indenter tip. Combining modeling and nanoindentation measurements at different temperatures and loading conditions, the deformation and the evolution of the interface between plastic deformation and elastic deformation regions were examined. The understanding of the size of the plastic zone and its growth during the indent gives insights into the deformation process taking place in the material, underpinning the application of nanoindentation creep to accelerated materials testing.
||Mechanical Properties, Nuclear Materials, Characterization