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Meeting 2018 TMS Annual Meeting & Exhibition
Symposium Computational Materials Science and Engineering for Nuclear Energy
Presentation Title Grain Growth and Grain Subdivision in Triuranium Disilicide, a Potential Light Water Reactor Fuel
Author(s) Amani Cheniour, Michael Tonks, Jie Lian, Yongfeng Zhang
On-Site Speaker (Planned) Amani Cheniour
Abstract Scope U3Si2 is a potential accident tolerant fuel for light water reactors. It has higher thermal conductivity and uranium density than UO2 . Grain growth can have important consequences on the fuel behavior and therefore needs to be studied at typical temperatures in a U3Si2 fuel pellet. Grain subdivision is characterized by the formation of a structure of nano-sized grains called the high burnup structure. It happens in UO2 below a certain temperature and above a certain burnup. This threshold needs to be determined for U3Si2. In this work, we compare the free energy of a system of large grains with high concentrations of radiation defects and fission gas atoms to the free energy of a system of nano-sized grains to determine this threshold. We use the MARMOT mesoscale fuel performance code to investigate both grain growth and grain subdivision. We will present our simulation approaches and current results.
Proceedings Inclusion? Planned: Supplemental Proceedings volume


A Model Coupling Hydrides Formation and Mechanical Behavior of Zircaloy Cladding during Fuel Rod Lifecycle
A Phase Field Study of Void Superlattice Formation in Irradiated Materials
A Quantitative Phase-Field Model for Gas Bubble Evolution in Nuclear Fuels
Ab Initio Modeling of Vacancy-type Defects in a High Entropy Alloy
Atomistic Modeling of Primary Damage in Fe-based Ferritic Alloys
Atomistic Study of Thermal Spike Response of Xe Bubbles in UO2
Breaking the Power Law: Multiscale Simulations of Self-ion Irradiated Tungsten
Calculating Free Energies of Metal-He Interfaces from Atomic Models
Cluster Dynamics in Irradiated Materials: A Hybrid Deterministic/Stochastic Coupling Algorithm
Competition of Deformation Modes in Irradiated Zr Alloys: A Micromechanical Approach
Computer Simulations of Dislocation-obstacle Interactions in the Hardening and Recovery of BWR-irradiated 304L SS
Density Functional Theory Simulations of Clusters in Reactor Pressure Vessel Steels
Density Functional Theory Study of the Magnetic Moment of Solute Mn in BCC Fe
Discrete Dislocation Sinks in Spatially Resolved Cluster Dynamics Simulations
Dislocation Loop Bias in BCC Fe
Effect of Dopants on Uranium-based Metallic Fuels to Mitigate Fuel-cladding Chemical Interactions
Effect of Post Fabrication Voids on Irradiation Performance of U-10Mo Monolithic Mini-plate
Effects of Oxygen on the Density of States and Elastic Properties of Hafnium—First Principles Calculations
Evolution of Grain Boundary Structure and Composition in Irradiated SiC
Experimentally Validated Computational Modeling of Advanced Alloys and Radiation Effects for Nuclear Energy Applications
Flux Effect on RIS in a Fe3%Ni Model Alloy: CD Modelling of the T Shift
Formation and Re-orientation of Multi-phase Zirconium Hydrides under Applied Strain
Fundamental Understanding of Corrosion of Nuclear Materials: Holistic Approach to Fuel Cladding Corrosion under Irradiation
Fundamentals of Energy Dissipation and Defect Energetics of Maximally Disordered Alloys
Grain Growth and Grain Subdivision in Triuranium Disilicide, a Potential Light Water Reactor Fuel
Hydrogen Transport and Trapping in Irradiation Damaged Zirconium Alloys
Interstitial-mediated Diffusion and Aggregation Mechanism for Transmutation Elements Rhenium and Ormium Precipitation in Tungsten
Kinetics of Point Defect Absorption by Sinks: Effect of Point Defect Properties and Surrounding Microstructure
Microstructure-sensitive Phase Field Fracture Model Including Anisotropic Elastic Properties
Modeling Inclusions with Surface Stresses in the Phase Field Framework
Molecular Dynamics Simulations of Effects of Stacking Fault Energies on Defect Formation Process in FCC Metals
Molecular Dynamics Study of Defect-grain Boundary Interactions in Irradiated PyC-like Configuration
Molecular Dynamics Study of Irradiation Damage in Nano-grain Sized Polycrystal
Morphological Study of Dispersion Phases in Heterogenous Waste Form Materials for Efficient Nuclear Waste Containment
Multiscale Simulations of Sequential Dislocation/Obstacle Interactions in FCC Metals
Off-stoichiometric Cluster Dynamics in Irradiated Oxides
Phase Field Modeling of Grain Boundary Evolution in Porous Oxides: Grain Growth and Pore Mobility Effects
Phase Transformation in Zirconium Oxide – A Mesoscale Study
Quantitative Phase Field Modeling of Void Growth in Irradiated Solids
Radiation Damage in Carbon-based Materials
Rate-theory Modeling of Irradiation Damage Cascades and the Influence of the Underlying Microstructure using the MOOSE Framework
Rate Theory Modeling of Fission Gas Behavior in Ion Implantation Experiment
Real-space Diffusion-driven Models for Microstructural Evolution of Irradiated Materials
Residual Point Defects and their Evolution near Dislocation Loops and Grain Boundaries in α-zirconium: An Atomistic Study
Simulation of Phosphorous Migration to Grain-boundary by Molecular Dynamics
Sink Density Effect on Radiation-induced Segregation and Precipitation in Fe-Cr Alloys
The Thermodynamic and Kinetic Properties of Spinels as They Relate to CRUD
Thermomechanical Analysis of the Multi-metallic Layered Composite Fuel Cladding for Improved Accident Tolerance of LWRs
Thermophysical Properties of (U,Zr)O2 Pellet-cladding Interface though MD Simulations
Using Computational Modeling to Interpret Experimental Measurements of Irradiation Induced Hardening in Metals
Vacancy Clusters and Xenon Diffusion in UO2

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