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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Informatics to Accelerate Nuclear Materials Investigation
Presentation Title Scanning-TEM (STEM) 3D Tomography for Quantification of Radiation Damage in Neutron Irradiated 316L Stainless Steel
Author(s) Laura Hawkins, Fei Xu, Mario D Matos, Tiankai Yao, Boopathy Kombaiah, Collin Knight, Yachun Wang
On-Site Speaker (Planned) Laura Hawkins
Abstract Scope Current transmission electron microscopy (TEM) characterization of radiation damage, such as dislocation loops and voids, is based on 2D projections of a 3D thin microstructure. Therefore, TEM-based quantitative knowledge of radiation damage is subject to various assumptions about the defect shape and sample thickness. This study uses automated Scanning-TEM (STEM) tomography to capture and characterize radiation damage in an EBR-II neutron-irradiated AISI 316L stainless steel to high doses. Coupled with machine learning models for 3D voxel segmentation and feature classification, the volume was reconstructed in a 3D space to show size, shape, and spatial distribution of defects. 3D visualization and data analysis provided ~20% more accurate counts of void density and dislocation loop distribution in the sample when compared to the traditional 2D method.
Proceedings Inclusion? Planned:
Keywords Characterization, Machine Learning, 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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