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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Informatics to Accelerate Nuclear Materials Investigation
Presentation Title Quantitative Insight to Fission Gas Bubble Distribution and Lanthanide Movement in Irradiated Annular U-10Zr Metallic Fuel Using Deep Learning
Author(s) Fei Xu, Yalei Tang, Lu Cai, Daniele Salvato, Shoukun Sun, Min Xian, Fidelma Giulia Di Lemma, Luca Capriotti, Tiankai Yao
On-Site Speaker (Planned) Yalei Tang
Abstract Scope U-10Zr Metal fuel is a promising nuclear fuel candidate for next-generation sodium-cooled fast spectrum reactors. Porosity is one of the key facts to impact the performance of metallic fuel. Additionally, a mechanical understanding of fission gas bubbles evolution behavior is a prerequisite for fuel development and qualification. Previous study of fission gas bubbles relied on a simple threshold method working on low resolution optical microscopy images, which has challenges in recognizing bubble boundaries, and caused inaccurate statistics of bubble properties. In this paper, a pre-trained deep learning model on Scanning Electron Microscopy (SEM) images from an annular U-10Zr fuel (AF1), was applied to another U-10Zr annular fuel (AF2). More accurate fission gas bubble segmentation results were generated, which leads to more precise qualitative analysis on the morphology, size, density, and orientation of bubbles. Furthermore, we investigated the lanthanide movement along the radial temperature gradient and obtained conclusive findings.
Proceedings Inclusion? Planned:
Keywords Machine Learning, Characterization, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerating Characterization of Radiation Driven Processes using Machine Learning Tools
Characterizing Microstructures in Aluminide Coatings Captured in SEM Image with Convolutional Neural Networks
Deep Neural Network for Porosity and Microstructure Analytics of a High Burnup U-10Zr Metallic Solid Fuel
Defect Evolution in Multi-principal Chemically Disordered Alloys from Multiscale Simulations
E-25: Feature Engineering for Construction of High-accuracy Thermal Conductivity Prediction Model for Uranium Compounds
E-26: Materials Genomics Search for Possible Helium-absorbing Nano-phases in Fusion Structural Materials and Experimental Validation
Emergent Molecular Structure and Dynamics of Tetrahedral Liquids Revealed by Neural Network Forcefield Simulations and Neutron Spin Echo Experiments
Few-shot Machine Learning for Automated Analysis of TEM Images of Nuclear Materials
Influence of Empirical Potentials on Data Quality in Computational Studies of Zr Alloys
Inverse Uncertainty Quantification of Dispersion Analysis Research Tool (DART) Parameters Necessary for the Calculation of Fission Gas Swelling in U-Mo Fuel
Machine Learning Enhanced Kinetic Monte Carlo Modeling of Molten Salt Corrosion of Ni-Cr Alloys
Machine Learning for Predicting Reactor Pressure Vessel Embrittlement
Materials Genomics Search for Helium-absorbing Nano-phases in Fusion Structural Materials
Modeling Cascade Damage in Tungsten Using Machine Learning SNAP Interatomic Potential: Electron-Phonon Interaction Model
Neural Networks of Defect Kinetics in Refractory Alloys
Optimizing Thermal Conductivity Prediction of Uranium Compounds using Balanced Multiclass Classification
Probing Radiation Induced Interface Metastability Using Deep Learning Object Detection
Putting Artificial Intelligence into Action to Quantify Radiation Effects in Materials
Quantitative Insight to Fission Gas Bubble Distribution and Lanthanide Movement in Irradiated Annular U-10Zr Metallic Fuel Using Deep Learning
Revealing the Story of Defects from Coupled Extreme Environments with Autoencoders and Dense Neural Networks
Scaling Ductility from Microscale to Bulk by Coupling Crystal Plasticity Simulations with 3D Convolutional Neural Networks
Scanning-TEM (STEM) 3D Tomography for Quantification of Radiation Damage in Neutron Irradiated 316L Stainless Steel
Synthetic Data Driven Materials Informatics Methods for Nuclear Materials Characterization
Utilizing Mechanistic Modeling and Uncertainty Analysis to Support Nuclear Fuel Qualification

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