| About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
|
| Presentation Title |
Microstructural and Chemical Evolution Studies of U-10Zr Metallic Fuel and HT9 Cladding from Fast Flux Test Facility |
| Author(s) |
Mukesh Bachhav, Daniele Salvato, Sohail Shah, Tiankai Yao, Luca Capriotti, Cameron Howard |
| On-Site Speaker (Planned) |
Mukesh Bachhav |
| Abstract Scope |
Metallic U-Zr alloys are candidate fuels for the next generation sodium-cooled fast reactors due their higher densities of fissile and fertile materials than most other fuel systems. Post irradiation microstructural and chemical examinations of fuel, cladding and fuel-cladding chemical interaction (FCCI) is important for evaluating the performance. In this study, high resolution studies are performed using transmission electron microscopy and atom probe tomography along the radial direction of fuel, inside the FCCI region as well as in the cladding region. The U-10Zr fuel is studied along the radial direction to elucidate redistribution of Zr and fission products. Studies are also performed on the FCCI region to investigate interaction of solute elements of fuels as well fission products with Fe and Cr from the cladding. APT studies are performed on HT9 cladding close to FCCI region to evaluate microstructural changes and re-distribution of Cr due to irradiation. |