| 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 |
The Fabrication, Advanced Characterization, Advanced Test Reactor Irradiation, Post Irradiation Examination, and Materials Informatics for Annular U-10Zr Metallic Fuel |
| Author(s) |
Tiankai Yao, Mukesh N. Bachhav, Fei Xu, Luca Capriotti, Benson Michael, Lingfeng He, Jason M. Harp |
| On-Site Speaker (Planned) |
Tiankai Yao |
| Abstract Scope |
To develop sodium cooled fast reactors metal fuel with capability of ultrahigh burnup of up to 30 – 40 at% (300 – 400 MWd/KgM), the Department of Energy Advanced Fuel Campaign has explored novel metallic fuel concepts. The fuel was fabricated, cladded with HT-9 at the Materials & Fuels Complex, and irradiated in the Advanced Test Reactors of Idaho National Laboratory to a peak burnup of 3.3% FIMA. The irradiation lasted for ~120 days in the reactor. This study presents the advanced characterization of both archived fresh fuel and ATR irradiated fuel using state of the art materials characterization method. We also applied computer vision machine learning algorithms to add informatics to the irradiation effects for metallic fuels, including the pore statistics and fuel cladding chemical interaction thickness distribution. Our works showcased that INL is the ideal place to test and develop fuel concepts for advanced SFR reactors. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Machine Learning, Phase Transformations |