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 |
Lower Length Scale Fuel Performance Modeling of U-Mo Fuel |
Author(s) |
Benjamin W. Beeler, Bei Ye, Zhi-Gang Mei, Yongfeng Zhang, Shenyang Hu, Maria Okuniewski, Sourabh Kadambi, Linu Malakkal |
On-Site Speaker (Planned) |
Benjamin W. Beeler |
Abstract Scope |
A monolithic fuel design with a U-Mo alloy has been selected as the fuel for conversion of the United States High-Performance Research Reactors (HPRRs). The accurate prediction of fuel evolution under irradiation requires the implementation of correct thermodynamic properties into mesoscale and continuum fuel performance modeling codes. As the physics that governs microstructural evolution span various time and spatial scales, understanding the fuel behavior inevitably involves atomic to mesoscale resolution that can be difficult to determine experimentally. Microstructural-level modeling and simulations can be used to develop physics-based materials models that can provide physical understanding to inform fabrication process control, as well as a valuable feedback mechanism between post-irradiation examination results and fabrication parameters. This presentation outlines recent lower-length scale modeling efforts that have been applied to address critical microstructural questions and provide mechanistic inputs for existing fuel performance codes to improve the descriptive and predictive capability at the engineering scale. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Computational Materials Science & Engineering, Modeling and Simulation |