|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||High resolution microscopic studies on HT-9 cladding from U-10Zr fuel irradiated at fast flux test facility
||Mukesh Bachhav, Tiankai Yao, Luca Capriotti, Jason Harp, Maria Okuniewski, Jonova Thomas, Yachun Wang
|On-Site Speaker (Planned)
The performance of metallic fuel in a fast reactor is known to be depended on several factors including fuel composition, microstructural changes in fuels, fission products distribution, and fuel-cladding chemical interactions (FCCI). Study on evolution of microstructural changes in FCCI layer is highly desirable for a greater phenomenological understanding of FCCI and fuel constituent redistribution. To that end, we investigated HT-9 cladding on U-10Zr fuel subjected to a local burnup of 5.7 atom percent and a local inner cladding temperature of 615 °C. Atom Probe Tomography (APT) and Transmission Electron Microscopy (TEM) is employed to investigate the distribution of fission products and microstructural changes in HT-9. Specimens for TEM and APT were prepared from different part of FCCI to elucidate chemical distribution of fission products and microchemical changes in HT-9.
||Nuclear Materials, Iron and Steel, Characterization