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Meeting Materials Science & Technology 2016
Symposium Materials Development for Nuclear Applications and Extreme Environments
Sponsorship NACE International
Organizer(s) Raghunath Kanakala, University of Idaho
Nan Li, Los Alamos National Laboratory
Todd R. Allen, Idaho National Laboratory
Jake Amoroso, Savannah River National Laboratory
Aladar A. Csontos, Nuclear Regulatory Commission
Lingfeng He, Idaho National Laboratory
Yutai Katoh, Oak Ridge National Laboratory
Josef Matyas, Pacific Northwest National Laboratory
Amit Misra, University of Michigan
Raul Rebak, GE Global Research
Kumar Sridharan, University of Wisconsin
Scope Global expansion of nuclear power to meet rising energy demand calls for the development of structural materials and fuels for advanced reactors. A related issue is the performance of materials under extreme conditions, such as elevated temperature, mechanical stress, high radiation dose and the presence of corrosive chemicals.
This symposium will address topics ranging from fundamental and applied science aspects of materials development for fission and fusion reactors to radiation detectors and extreme environments. In addition, the symposium will also focus on lifetime extension of existing nuclear reactors and meeting the challenges of future nuclear endeavors. A key goal is to discuss the radiation response of all classes of materials—metals, ceramics, semiconductors, polymers and composite materials—to discover linkages and common threads. In recent years, by virtue of the state-of-the-art experimental techniques, such as in situ irradiation irradiation in a transmission electron microscope (TEM), sub- level spatial resolution in spectroscopy in TEM, 3D atom probe tomography, synchrotron x-ray diffraction, ion beam analysis, etc, new insights is being obtained on the atomistic-level mechanisms of radiation damage in solids. Additionally, advances in computational approaches at the atomistic and meso-scales are enabling simulations of radiation damage mechanisms across multiple length and time scales. Presentations that combine experiment with theory, modeling and simulation to enhance our understanding of radiation effects in materials are especially encouraged.
Abstracts are solicited in (but not limited to) the following topics:
• Flow Assisted Corrosion (Materials aspects and NDT techniques)
• Fundamental science of radiation damage and defect processes
• Materials for extreme environments
• In situ irradiation in a TEM
• Atomistic scale modeling of radiation induced defects and structure evolution
• Small scale mechanical and thermal characterization of irradiated materials
• Advanced nuclear fuels
• Accident tolerant cladding and fuels materials
• Advanced structural materials
• Ion irradiation effects in materials
• Radiation effects in nanomaterials
• Aging, degradation and thermodynamic studies
• Reactor and shield design
• Microstructure/property relationships in irradiated materials
• Thermal conductivity degradation
• Nanotechnology in nuclear engineering
• Materials for radiation detection
• Theory, modeling and simulation of radiation effects
• Hybrid Energy: Nuclear and other energy sources
Abstracts Due 03/31/2016
Proceedings Plan Planned: Publication outside of MS&T

Annular Accident Tolerant Fuel with Disc Inserts
Atomistic Simulations of Dislocations in Zirconium Alloys
CALPHAD Assessment of the Carbon-zirconium System
Characterization of the Effects of Carbide Precipitates and Spinodal Decomposition on Thermal Aging Embrittlement of Cast Duplex Stainless Steels
Characterizing Ion Irradiation Damage in Structural Metals using Spherical Nanoindentation Stress-Strain Curves
Cluster Evolution in F/M Alloys upon Neutron, Proton, and Self-ion Irradiation
Controlling the Permeability of Corrosion Inducing Ions in the Concrete by Nano-viscosity Modifiers: An EIS Study
Corrosion Behavior of U3Si2 in Pressurized Water at 300°C
Coupling Radiation Damage from Binary Collision Monte Carlo to Phase Field Microstructure Evolution
Damage Accumulation in Ni-based Concentrated Solid-solution Alloys under Prolonged Irradiation
Development of a Multi-component (Al, Am, Fe, Ga, Ni, Pu, and U) CALPHAD Database for Complex Actinide-based Systems
Development of Advanced Ferritic Steels for Fast Reactor Applications
Development of Zirconium-silicide Coating for Enhancement of Accident Tolerance of Zirconium-alloy LWR Cladding Material
D. T. Rankin Award Lecture: Thermochemical Modeling of Nuclear Fuel and Its Use in Fuel Performance Codes
Effect of Crack-tip Stress Field on Delayed Hydride Cracking
Effect of Crystallographic Texture on Creep Rupture Behaviour of 9Cr-1Mo Steel
Effects of Ion-irradiation Damage on Mechanical Behavior in Silicon Carbide
Effects of the Two-temperature Model on Cascade Evolution in Ni and Ni-based Alloys
Efficient Deterministic Simulation of Phonon Transport in Nuclear Materials
Experimental Solubility of Lanthanides in Liquid Sodium
Fabrication Development Efforts in Support of the Accident Tolerant Fuel Program
Fretting Studies of Accident Tolerant FeCrAl Cladding
Grain Boundary Dependence of Radiation Induced Damage in Nanocrystalline Nickel and Nickel-chromium Thin Films
Identification of Ag-rich Phase in TRISO Fuels by Using Atom Probe Tomography
Influence of Compositional Changes on Defect Evolution in Advanced Alloys
Investigation of Pressure Resistance Welding for Thin-walled Accident Tolerant Fuel Claddings
Irradiation Induced Defects in Titanium Dioxide for Energy Storage Applications
Long Duration CVD Fabrication of Mo Tubes for Nuclear Fuel Cladding
Microstructures and Strength of Early Nuclear Grade SiC/SiC Composite after Very High Fluence Neutron Irradiation
Molecular Dynamics Simulation of Defect Production in FeCr Alloys
Neutron Irradiation of Ti3AlC2 -Ti5Al2C3 and Ti3SiC2 Materials
New ODS FeCrAlYZr Alloys for Accident Tolerant Fuel Cladding
Online Monitoring of Passive Components and Structures in Nuclear Power Plants: From Offline Periodic Inspections to Online Real Time Surveillance
Oxide Dispersion Strengthened Steel and Silicon Carbide Composite Cladding Materials
Precipitation Modeling in Nuclear Steels with Cluster Dynamics
Pyrolytic Carbon Coatings on Oxide and Carbide Microspheres
Radiation Damage Behavior in Multiphase Ceramics
Reducing Risks in Nuclear Power Plants Operation by Using FeCrAl Alloys as Fuel Cladding
Role of Interfaces on Microstructural Stability of Cu-Nb Nanocomposites Subjected to High Pressure Torsion
Stabilization of Zrn+1AlCn MAX Phases; Issues and Achievements
Surface Modification of Zircaloy-4 for Isotope Producing Target Designs
Synthesis, Sintering, and Hydrothermal Corrosion Studies of Advanced Multiphase Actinide Fuels
Thermal Conductivity of Multiphase Ceramics for an Inert Matrix Fuel
Ti-Al-C MAX Phase Coatings for Accident Tolerant Fuels
Understanding Hydride Formation in Alpha-Zr at the Atomic Scale

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