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Meeting 2022 TMS Annual Meeting & Exhibition
Symposium Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
Sponsorship TMS Structural Materials Division
TMS: Advanced Characterization, Testing, and Simulation Committee
TMS: Energy Committee
TMS: Nanomechanical Materials Behavior Committee
TMS: Nuclear Materials Committee
Organizer(s) David Frazer, Idaho National Laboratory
Fabiola Cappia, Idaho National Laboratory
Tsvetoslav Pavlov, Idaho National Laboratory
Peter Hosemann, University of California
Scope Evaluating the evolution of nuclear fuel during reactor operation is essential to foster the scientific understanding of fuel behavior. This can provide the data needed to enhance the burn-up of current fuels, enable the use of new accident tolerant fuel forms and metallic fuels. With this research motivation many research facilities worldwide have developed their ability to characterize fresh and irradiated fuels utilizing advanced electron microscopy and thermal characterization techniques.

The application of these techniques has led to fuels being studied before and after service providing new knowledge and ideas to enhance burnup and fuel utilization or investigate new fuel forms. In addition, these tools have been applied to evaluate the movement of fission products and further the understanding of the fuel clad chemical interactions and are now ready to be deployed in other fields of research as well.

In parallel, model development and implementation of the data generated with advanced techniques in physics-based models for fuel performance codes is becoming increasingly important, both for current fuel burnup extension and advanced fuel development.

This symposium aims to take a closer look at the evolution of the microstructure and thermo-physical properties of nuclear fuels during service, including the interaction region between fuel and cladding. Correspondingly, the synergy with materials modeling in advancing and understanding fuels performance under normal and accident conditions will be considered in the symposium.

Topics of interest include, but are not limited to:
Scanning electron microscopy characterization of nuclear fuels and its associated techniques such as Energy dispersive spectroscopy and Wavelength-dispersive X-ray spectroscopy and Electron backscatter diffraction
Transmission electron microscopy characterization of nuclear fuels
3D reconstructions of electron backscatter diffraction or scanning election microscopy images of nuclear fuels
Thermo-physical property measurements of both fresh and irradiated nuclear fuels
Modeling of nuclear fuel behavior during operation

Abstracts Due 07/19/2021
Proceedings Plan Planned:
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

3D Reconstruction and Quantification of Oxide Nano-porosity in Zirconium Alloys
A combined molecular and cluster dynamics approach to determine radiation enhanced diffusion in UMo alloys
A Monte-Carlo solver for coupled electron-phonon Boltzmann transport equation in metallic α-U
A Predictive Approach to Model Thermal Conductivity Degradation For In-Pile UO2
Accelerating Nuclear Fuel Qualification through Multiscale Models
Adding irradiation-assisted grain growth to the MARMOT tool for UO2 nuclear fuel
Advanced Characterization of Oxidation Behavior of TRISO Fuel SiC Coating
An atomistic study of the anisotropic elastic response of defects in alpha uranium
An atomistically-informed cluster dynamics approach for defect evolution in ThO2 under irradiation
An Experimentally Validated Mesoscale Model for the Effective Thermal conductivity of UZr Fuels
An Integrated Approach for Coupling Experimental Data, Physics-based Models, and Machine Learning Algorithms for Predicting the Effective Thermal Conductivity of U-based Fuels
Atomistic modeling of Ag transport through ∑9 {122} grain boundary of cubic SiC via molecular dynamics
Atomistic modeling of transport properties and interaction with point defects of α-U tilt grain boundaries
Bulk thermal conductivity measurement of fuels and surrogates
Centipede: A New Tool for Calculating Irradiation Enhanced Transport of Defects in Nuclear Fuel
Characterization of additively manufactured UO2 fuel pellets with pulsed neutron techniques and 450 keV X-ray CT
Characterization of Nuclear Materials from the Millimeter to the Nanometer
Comparison of Observations from the Microstructure of Two High Burnup Fuel Samples Operated at Different Linear Heat Generation Rates
Computer Vision Application for in-situ Transmission Electron Microscopy of Irradiation Process
Correlating atomic scale microstructure with mechanical properties in low-density pyrocarbon used in TRISO particle fuel buffer layer
Correlating irradiation-induced thermal conductivity modification with structural disorder in intermetallic compounds.
Correlative APT-TEM investigation of defects’ influence on thermal diffusivity in ThO2 nuclear fuel
Diffusion coefficients of Zr- and Cr-based binary systems for simulation of Cr-coated Zircaloy nuclear fuel cladding
Evolution of the internal layer structure in irradiated TRISO fuel
Experimentally validated model for investigating high-burnup structure formation in U-Mo fuels
Fabrication and characterisation of an innovative advanced technology fuel: coated UN microspheres embedded in UO2 matrix
High-resolution thermal conductivity and thermal boundary resistance mapping in TRISO
High-Throughput Viscosity Measurements of Molten Salts for Molten Salt Reactors
Investigation of damage structure evolution on proton irradiated Zr-alloys of various compositions using synchrotron X-Ray Diffraction and TEM
Investigation of Hot-cell Capable Thermal Conductivity Measurements for Ceramic Fuels
Investigation of the Impact the 3D Fission Product Structure has on the Local Thermal Conductivity in FBR MOX Fuel
Mesoscale Hybrid Model for Fission Gas Behavior in UO2: Coupling the Phase Field Method to Spatially Resolved Cluster Dynamics
Mesoscale model of gas bubble evolution and creep in monolithic UMo fuels
Mesoscale Modeling of Effective Thermal Conductivity in U-Zr Fuels with Heterogeneous Phases
Micromechanical behavior of thermally loaded monoclinic U-6Nb
Microstructural characterization of the porous pyrocarbon buffer layer in TRISO fuel particles
Microstructure and thermophysical properties of simulated high burnup structures of UO2 made by flash sintering
Modeling irradiation-enhanced diffusion in advanced ceramic nuclear fuels
Modifying process windows to control secondary phase formation and phase transformations at U-10Mo/Zr interfaces
Multiphysics Modeling of Fracture in Sintered Uranium Dioxide Pellets
Neutron Radiography at LANSCE: Interrogating and Characterizing Materials for Next Generation Nuclear Reactor Designs
On the phases observed in irradiated U-19Pu-14Zr fuels
Perspectives on Synchrotron Micro-Computed Tomography and Serial Sectioning Applied to Metallic Nuclear Fuels
Predicting thermophysical properties of actinide oxides using atomic scale simulation"
Propose Advanced Nuclear Fuels with High Thermal Conductivity Using Machine Learning
Pulsed Neutron Characterization of Irradiated Fuels at LANSCE
Structural analysis of the IPyC/SiC interface of AGR-2 irradiated and safety tested TRISO fuel
Synergistic electron/thermal microscope for high-throughput screening of emerging nuclear materials
The effect of the proton irradiation dose rate on the evolution of microstructure in Zr alloys: a synchrotron micro-beam X-ray and TEM study
The influence of radiation-induced microstructural defects on the optical and elastic properties of ceramic nuclear fuels
Thermal conductivity degradation by solid fission products: Machine learning coupled with first principles model.
Thermal Conductivity Measurement of Microstructures in Irradiated Nuclear Fuels
Thermal energy transport in defect-bearing and uranium-doped single crystal thorium dioxide
Thermal Stability of Uranium Compounds and Advanced Nuclear Materials under Extreme Conditions
Thermal Transport Behavior of Pristine and Zirconium-doped Alpha-Uranium
Thermo-physical properties of the ternary (U2Cr)N3 phase


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