ProgramMaster Logo
Conference Tools for 2016 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 Symposium
Meeting 2016 TMS Annual Meeting & Exhibition
Symposium Computational Materials Engineering for Nuclear Reactor Applications
Sponsorship
Organizer(s) Michael Tonks, Pennsylvania State University
Julie D. Tucker, Oregon State University
Mark Tschopp, Army Research Laboratory
Richard Williamson, Idaho National Laboratory
Scope The future of nuclear energy can potentially look very different than it does today. New accident tolerant fuel concepts are being developed for a broad range of reactors, including light water reactors (LWRs) and small modular reactors. However, material performance defines the efficiency, safety, and commercial feasibility of all reactor concepts. With recent improvements in modeling and simulation across a wide range of length- and time-scales, computational materials modeling will play a critical role in understanding current reactor technology and in developing new reactor concepts. This symposium will highlight current computational materials engineering efforts for nuclear reactors in the United States and abroad, e.g., the Consortium for the Advanced Simulation of LWRs (CASL) and the Nuclear Energy Advanced Modeling and Simulation Program (NEAMS).

This symposium is seeking abstracts that apply atomistic, mesoscale, and macroscale simulations to discover, understand, and engineer the performance of fission/fusion reactor materials, including fuel, cladding, and structural materials. This symposium will also consider multiscale modeling efforts that bridge length and time scales in order to better connect simulation results with experimental data for predictive model validation. Finally, the application of ICME approaches to use modeling and simulation to better understand structure-property relationships, their associated links with performance, and their application to designing future reactor concepts and materials is also desired. Some examples include, but are not limited to:

- Developing improved material models for LWR fuel and cladding
- Modeling and simulation of critical phenomena in LWRs including CRUD-induced power shift, grid-to-rod-fretting, and pellet-cladding interaction
- Modeling and simulation of new fuel materials including metal, silicide, and nitride fuels
- Modeling and simulation of new cladding materials, such as silicon carbide, coated zirconium alloys, or FeCrAl
- Development and integration of computational tools, methods, and databases for reactor structural material design
Abstracts Due 07/15/2015
Proceedings Plan Planned: A print-only volume
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

3D Phase Field Simulation of Grain Growth in Porous UO2
An Overview of the Fuel, Materials and Chemistry Focus Area within the CASL Energy Innovation Hub
Analysis of the Candidate Alternative Fuel Cladding FeCrAl during LWR Operation Using the BISON-CASL Fuel Performance Code
Cluster Dynamics Modeling of Damage Evolution in Iron Chrome Alloys
Cluster Dynamics Modeling of Extended Defects in Irradiated UO2 with Off-stoichiometry Considerations
Computational Materials Engineering for Reactor Applications Using the Open-Source MOOSE Framework
Computer Modeling of Hydrogen and Oxygen Transport during Zirconium Corrosion
Coupled Micro/Meso/Macro Modeling of the Crud Source Term in Light Water Reactors
Coupled PWR Oxidation Modeling with the HOGNOSE Code
Coupling Radiation Damage from Binary Collision Monte Carlo to Phase Field Microstructure Evolution
Development and Application of Accident Tolerant Fuel Models
Development of the NEAMS Fuels Product Line
Enhanced Helium Clustering Process in Iron
First Principles Neural Networks and Diffusion in Nuclear Structural Materials
Long-Term Defect Evolution in Iron-based Alloys from SEAKMC Simulations
Microstructure-explicit Rate Theory Modeling of Point Defect Transport during Irradiation Damage
Molecular Dynamics Simulations on Homogeneous Hydride Nucleation in Alpha-Zr
Multi-scale Simulation of Fission Gas Diffusion in UO2 Nuclear Fuel
Multiscale Modeling of the Coherency Loss of Hydrides in αZr
One Dimensional Migration and Gas Bubble Superlattice Formation in UMo Metal Fuels--a Phase-field Model
Optimization of Self-interstitial Clusters in 3C-SiC Using Generic Algorithm
PCI Analysis of a Commercial PWR using Bison-CASL Fuel Performance Code
Phase-field modeling of ODS particle behavior in the metallic system.
Predicting the Radiation Dependent Flow Stress and Cleavage Failure in RPV steels using Crystal Plasticity
Role of Stoichiometry on Ordering in Ni-Cr Alloys
Silicon and Vacancy Diffusion near an Edge Dislocation in Nickel under Irradiation
Stochastic Modeling of the Corrosion of Zirconium and its Alloys: Theory and Application to Autoclave Corrosion
Structural Integrity Analysis of Reactor Pressure Vessel with Lamellar Flaws in Grizzly
Thermo-Mechanical Analysis of SiC/SiC Composite Cladding for LWR Application.
Thermodynamic Modeling of Complex Oxide Phases in U-M-O Systems where M = Ce, Nd, Pr, La, Y, Gd, and Th
Validation of BISON Calculation of Hydrogen Distribution by Comparison to Experiment
Z-10: Texture Measurement and Prediction of Rolled α-uranium Foil
Z-11: Using Phase Field Modelling to Investigate the Bubble Lattice Phenomenon in Nuclear Fission Materials
Z-1: A Spatially Resolved Stochastic Cluster Dynamics Approach for Simulating Radiation Damage Accumulation in α-Fe
Z-2: Ab initio Study of Native Defects Near the Stacking Faults of 3C-SiC
Z-3: Beryllium Segregation to Zr(0001) Surface by First Principles
Z-4: Cluster Dynamics Modeling of Coupling of Cu-rich and Mn-Ni-Si Precipitates in RPV Steels
Z-5: Computational Modeling of the Structure of Jogged Screw Dislocations Responsible for Zircaloy Creep
Z-6: Dislocation Loop Sink Strengths: A 3D Phase-field Modelling Including Realistic Anisotropic Effects
Z-7: Gas Bubble Kinetics in an Irradiated U-Mo Using a Multistate Simulation Approach
Z-8: Phase Field Model of Multiphase Hydrides in Zirconium Fuel Rod Claddings
Z-9: Sensitivity Analysis of Rate Equations and Kinetic Monte Carlo Models


Questions about ProgramMaster? Contact programming@programmaster.org