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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Informatics to Accelerate Nuclear Materials Investigation
Presentation Title Inverse Uncertainty Quantification of Dispersion Analysis Research Tool (DART) Parameters Necessary for the Calculation of Fission Gas Swelling in U-Mo Fuel
Author(s) ATM Jahid Hasan, Zhi-Gang Mei, Bei Ye, Benjamin Beeler
On-Site Speaker (Planned) ATM Jahid Hasan
Abstract Scope Accurate prediction and understanding of fission gas swelling (FGS) are essential for fuel qualification of U-Mo monolithic fuel. The Dispersion Analysis Research Tool (DART), a rate-theory-based code developed at Argonne National Laboratory, provides a way to calculate FGS in U-Mo. However, DART utilizes assumed values for some lower-length-scale fuel parameters of U-Mo that are still unknown. Estimation of these parameter distributions is crucial for FGS prediction. This study performs inverse uncertainty quantification to obtain posterior probability distributions (PPDs) of DART parameters. Initially, surrogate models based on neural networks, gaussian processes, and other machine learning methods are built using the available data from DART. Bayesian inference methods, such as Markov Chain Monte Carlo, are then applied to find the parameter PPDs. Finally, the surrogate models are used to compute the push-forward of the parameter PPDs. This work concomitantly establishes a way to perform sensitivity analysis and optimization of DART parameters.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Computational Materials Science & Engineering, Modeling and Simulation

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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