ProgramMaster Logo
Conference Tools for 2024 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Informatics to Accelerate Nuclear Materials Investigation
Presentation Title Optimizing Thermal Conductivity Prediction of Uranium Compounds using Balanced Multiclass Classification
Author(s) Yifan Sun, Masaya Kumagai, Yuji Ohishi, Eriko Sato, Masako Aoki, Ken Kurosaki
On-Site Speaker (Planned) Yifan Sun
Abstract Scope In the pursuit of advanced nuclear fuels, a multiclass classification model was applied to predict the thermal conductivity of uranium compounds. We used element properties (Magpie) and temperature as features, with thermal conductivity data, sourced from the Starrydata2 database, classified into three ranges. However, the class distribution in the Starrydata2 database is skewed towards materials with low thermal conductivity, heavily biasing the model’s predictions towards lower values. This imbalance posed a challenge in identifying nuclear fuels with high thermal conductivity. To mitigate class imbalance, we employed the Synthetic Minority Oversampling Technique and Random Undersampling to balance the training data. As a result, the bias towards underestimating thermal conductivity was reduced, with recall for classes 1 (5-15 W/mK) and 2 (15+ W/mK) increasing from 0.33 and 0.64 to 0.49 and 0.71, respectively. By enhancing the model’s recall, our chances of discovering fuels with high thermal conductivity have significantly improved.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Machine Learning, Characterization

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

Questions about ProgramMaster? Contact programming@programmaster.org