| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
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| Symposium
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Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
High Resolution Microscopic Studies on HT-9 Cladding from U-10Zr Fuel Irradiated at Fast Flux Test Facility |
| Author(s) |
Mukesh Bachhav, Tiankai Yao, Luca Capriotti, Jason Harp, Maria Okuniewski, Jonova Thomas, Yachun Wang |
| On-Site Speaker (Planned) |
Mukesh Bachhav |
| Abstract Scope |
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. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Iron and Steel, Characterization |