|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Thermal Property Characterization, Modeling, and Theory in Extreme Environments
||Thermal Transport Behavior of U-50Zr at the Mesoscale: Before and After Irradiation
||Zilong Hua, Tiankai Yao, Amey Khanolkar, Cody Dennett, Xiaxin Ding, Krzysztof Gofryk, Michael Benson, Lingfeng He, Jian Gan, David Hurley
|On-Site Speaker (Planned)
The U-Zr based metallic fuel is a promising candidate for the next generation of fast reactors. Accurate knowledge of thermal conductivity degradation under irradiation is key to understanding microstructural evolution and fuel performance. It is thus necessary to investigate thermal transport on the scale of damage accumulation. In this talk, recent research results of intragranular thermal conductivity in three U-50Zr phases, γ-, ω-, and δ-, and the influence of ion-irradiation, are reported. Our results reveal that different microstructures associated with the three phases are explicitly reflected in the thermal transport behavior of the pristine samples. Specifically, the hexagonal δ-phase shows significant thermal anisotropy. After irradiation, the thermal transport behavior of the three U-50Zr samples changes significantly. Transmission electron microscopy is used to understand the impact of irradiation microstructure on thermal conductivity. These new insights are expected to aid in fuel performance modeling and fuel design.