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Meeting 2020 TMS Annual Meeting & Exhibition
Symposium Radiation Effects in Metals and Ceramics
Presentation Title Influence of Zircaloy Alloying Elements and Impurities on Point Defects Formation in ZrO2 Corrosion Films and Resultant Zircaloy Corrosion Rate
Author(s) William H. Howland, Richard W. Smith, Bruce F Kammenzind, Mikael Christensen, Volker Eyert, Erich Wimmer
On-Site Speaker (Planned) William H. Howland
Abstract Scope A typical composition of nuclear-grade zirconium alloys is more than 98 percent zirconium and less than 2 weight percent of tin, niobium, iron, chromium, nickel and other metals. A percentage of these impurities go into solution in the corrosion based zirconium oxide film. The alloying elements in zirconia solution will demand a response from intrinsic point defects such as oxygen anion vacancies and conduction band electrons. Additionally, contaminants such as Nitrogen can greatly enhance corrosion rates as point defects in zirconia by both influencing transport of corrosion species through the protective oxide barrier layer, by influencing corrosion transition, or both. To this end, this work determines the influence of Nitrogen on the transport properties of oxygen anion vacancies and conduction band electrons and the mitigating effects of common alloying elements such as Sn and Nb. The evolution of these point defects under irradiation is discussed.
Proceedings Inclusion? Planned: Supplemental Proceedings volume

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A New Numerical Method to Simulate Dislocation Self-climb
Advanced Electron Microscopy Characterization of Ion Radiation Damage in Bulk Metallic Glass and High Entropy Alloys
Alpha-alpha' Decomposition at Grain Boundaries in Annealed and Irradiated ODS Steels
Analysis of Neutron Irradiation Induced Element Redistribution in Ceramic and Metallic Alloy TPBAR Components
Applications of Advanced Electron Microscopy to Understand Irradiation Damage of Fusion and Fission Materials
Atom Probe Examinations of Zircaloy Irradiated at Nominally 410C
Atomistic Modeling of Radiation Resistance in Concentrated Alloys
BCC-FCC Interface Leading to Ni Precipitation under Irradiation in a FeNi Alloy
Characterizing Self-ion Irradiated Tungsten: Nano-indentation, Multi-technique Microscopy and Crystal-plasticity Modeling
Comparison of In-situ Micro- and Ex-situ Meso-scale Tensile Testing of As-fabricated HT-9 Steels
Comparison of the Irradiated Microstructure Formed in 800H After Neutron Irradiation and Dual Beam Ion Irradiation
Comprehensive Evaluation of the Degradation of Duplex Stainless Steels in Light Water Reactor Systems
Coupled Irradiation Induced Grain Growth and Damage Evolution in Solute Stabilized Nanocrystalline Tungsten
Data-driven Discrete Dislocation Dynamics Modeling of Yielding Behavior of Irradiated FeCrAl Steel
Defects Generation during Irradiation-induced Alpha/Gamma Phase Transformation in Uranium Alloys
Depth-dependent Characterization and 3D Tomography of In-situ Ion Irradiated Microstructure
Design and Results of the Irradiation Corrosion Experiment (ICE)
Dose Rate and Temperature Effect on the Stability of Alpha Prime Precipitates in Ultra-high Purity Fe-Cr Alloys
Dual Beam Irradiation of Tungsten Materials: Synergistic Effects and Comparison with Sequential and Single Beam Irradiation
Effect of Chemical Compositions on Precipitate Coherency Loss After In-situ Irradiations
Effects of Chemical Complexity and Radiation Parameters on Defect Evolution in Nickel-based Concentrated Solid Solution Alloys
Effects of Radiation Parameters on Defect Evolution in FeCrAl Alloys under Single-, Dual- and Triple-Ion Beam Irradiation
Elucidating Atomistic Mechanisms for Interface- and Grain Boundary-mediated Radiation Defects Annihilation
Enhanced Austenite Stability in Nanostructured Steels During Ion Irradiation
Future: Fundamental Understanding of Transport Under Reactor Extremes
H-21 (Digital): Evidence of Radiation Enhanced Diffusion via In-situ Ion Irradiation of Yttria Stabilized Zirconia Nanoparticles
H-22 (Digital): Helium Irradiation Induced Ultra-high Strength Nanotwinned Cu with Nanovoids
H-23: Coupled Electronic and Nuclear Stopping Effects on Damage Accumulation in SiC
H-24: Damage Evolution in Apatite Irradiated with Alpha Emitters
H-25: Deep Ion Implantation at the 88-Inch Cyclotron
H-26: Defect Clustering in Irradiated Alpha Uranium: Cluster Dynamics Modeling and Ion Irradiation Experiments
H-27: Defect Ordering in Yttria Stabilized Zirconia under 45 MeV Ion Irradiation
H-28: Effect of Ion Beam Irradiation on Microstructure Evolution of a Multi-metallic Layer Composite Material for Accident Tolerant Fuel Cladding Development
H-29: Electronic Effects in Molecular Dynamics Simulations of Ion Irradiation of SiC
H-30: Equilibrium and Irradiation-induced Point-defect Disorder in ThO2 and U-doped ThO2: Modeling and Ion Irradiation Experiments
H-31: Gamma-radiation Induced Corrosion of Copper
H-32: Ionization Induced Changes in Carbon Bonding of Graphite
H-33: Irradiation Behavior of Piezoelectric Materials for Nuclear Reactor Sensors Applications
H-34: Meso-, Micro-, and Nano-scale Characterization of Neutron Irradiated U-10Zr Metallic Fuels via Synchrotron µ-CT and Electron Microscopy
H-35: XCT Characterization of Neutron Irradiated SiC-SiC Composites
H-36: Combined Use of In-situ Ion Irradiation and In-situ Nanomechanical Testing for Characterizing Helium Pre-implanted 304 Stainless Steel
H-37: Coupled Bulk and Grain Boundary Compositional Patterning in Binary Immiscible Alloy under Irradiation: A Phase Field Modeling Study
H-39: Doppler Broadening Positron Annihilation Spectroscopy for Understanding Void Formation in Neutron Irradiated Fe-Cr Alloys
H-40: Effect of Ordered Helium Bubbles on the Deformation and Fracture Behavior in Zr
H-41: Elucidating the Role of Dispersoids on the Bulk and Nano-mechanical Properties of Dispersion-strengthened W Alloys Following Ion Irradiation with In-situ Characterization
H-42: Evaluation of Bubble Layers in Single- and Poly-crystal Tungsten after Helium Exposure
H-43: Exploring Stability of Nanocrystalline Metals with Competing Solute Effects under High Temperature Irradiation
H-44: Generalized Dislocation Mobility Law for BCC FeCrAl Alloys
H-46: How to Improve an Irradation-simulation Testbed
H-48: Influence of Grain Size and the Presence of Nano Oxides on the Radiation Resistance of a FeCrW Alloy
H-49: Investigating Radiation Damage in Metallic and Ceramic Materials for Advanced Nuclear Systems Using JANNuS Multiple Ion Beams
H-50: Ion-irradiation-induced Structural Disorder and Thermal Conductivity Changes of Intermetallic Compounds
H-51: Ion Irradiation Effects on the Microstructure of PM-HIP Inconel 625
H-52: Irradiation Induced Damage Evolution in Tungsten
H-53: Material Irradiation and Investigation Capabilities at TRIUMF
H-54: Mechanical Response of FeCr Alloys under Thermal Aging and Irradiation
H-55: Microstructural Response of FeCr/Y2O3 Bilayer System to He/H Implantation
H-56: Modeling Slip-induced Crack Initiation in Nickel Containing Nano-scale Helium Bubbles
H-57: Molecular Dynamics Simulation of Irradiation Damage in Disordered Alloys with Ordered Precipitation
H-58: Neutron Radiation Induced Patterning of Fe-Cr System: A Phase-field Approach
H-60: Radiation Damage Mechanisms in the Oxides Formed on Zr Alloys
H-61: Radiation Tolerance in Stabilized Alumina Coatings: an In-situ Irradiation Study
H-62: Radiation Tolerance of Gradient Grain-structured Copper
H-63: Small Scale Tensile Testing of Grain Boundary Strength of Pristine and Neutron Irradiated Ni Based X-750 Alloy
H-65: Tungsten Transmutation Products from Mixed Spectrum Neutron Irradiation
High Irradiation Resistance of Nanocrystalline W-based High Entropy Alloy
High Temperature Small Scale Mechanical Testing and Nanoindentation of Advanced Accident Tolerant Fuels
Influence of Alloying Elements on Microstructure Evolution in 21Cr32Ni Model Alloy Microstructure after In-situ Ion Irradiation
Influence of an Addition of Titanium and Carbon on the Microstructural Evolution under Irradiation of Nickel as Model Alloy for Austenitic Steels
Influence of Zircaloy Alloying Elements and Impurities on Point Defects Formation in ZrO2 Corrosion Films and Resultant Zircaloy Corrosion Rate
Investigating the Influence of Cu Rich Precipitates (CRPs) on the Formation of Complex Mn-Ni-Si Rich Precipitate Phases using Density Functional Theory (DFT)
Investigation of High Burnup Ceramic Fuel Microstructure at Idaho National Laboratory
Investigation of the Stability of Irradiation Induced MnNi Clusters by Post Irradiation Annealing
Ion Beam Synthesis of Nano-metallic Oxide Particles in High Purity FeCr
Irradiation Damage Behavior in Novel High-entropy Carbide Ceramics
Irradiation Effects in Weld Repairs of Irradiated Stainless Steel
Irradiation Enhanced Alpha Prime Precipitation in 2nd Gen. FeCrAl Alloys After Neutron Irradiation to 7 dpa
Irradiation of 14YWT Solid State Capacitive Discharge Welds
Mechanical Properties of Irradiated Cladding Material from BOR-60 Irradiations
Metal-ionic Phase Reactions in Molten Salt ionic Liquids: Experimental, Thermodynamic and Kinetic Analysis of the Alteration of Preformed-oxides on Fe-Cr and Ni-Cr Alloys
Microstructural Changes in Graphite and the Corresponding Bulk Property Evolution
Microstructural Characterization of Nuclear Graphite Irradiated at Temperatures below 230˚C
Microstructural Characterization of the Through-wall Thickness Pressure Vessel Weldment of the Zion NPP
Microstructural Investigation of Flux Effect on Neutron-irradiated RPV Steels
Microstructure and Mechanical Properties of Neutron Irradiated Tungsten Fibers for Fusion Applications
Microstructure and Microchemistry Characterization of Neutron Irradiated M5® and X2® Fuel Cladding
Nanoscale Characterisation of Re/Os Precipitation and Mechanical Degradation In Neutron Irradiated Tungsten
Near-surface Disorder in 4H-SiC Induced by MeV light Ion Irradiation
Neutron Irradiation Induced Intergranular Fission Product Precipitation in SiC Layer of TRISO Fuel
Neutron Radiation Damage of β Phase and its Impact on In-core Corrosion of Zr-Nb alloy
Noble Gas Bubble Superlattice in bcc Metals under Irradiation
Probing Thermal Diffusivity Degradation and Point Defect Density in self-ion Implanted Tungsten with Transient Grating Spectroscopy
Quantitative Analysis of Atomic Scale Defects in Irradiated Materials
Radiation Effects on Phonon Transport in UO2 and ThO2
Radiation Response of Grade 92 Ferritic-martensitic Steel Irradiated up to 14.63 dpa at ~700°C
Raman Signature of Point Defects in Boron Carbide
Reassessment of TRIM Simulations for Damage Production in Materials
Response of Solidification Cellular Structures in Additively Manufactured 316 Stainless Steel to Heavy Ion Irradiation: an In situ Study
Separate Effects to Integral Effects - All Things Radiation Effects in FeCrAl
Solute Stabilization of Two-phase Microstructures in Irradiated Alloys
Structural and Chemical Heterogeneities at the Nanoscale affecting Passive Film Formation during Irradiation and Corrosion
Studies of High dpa Ion Beam Irradiation fcc-bcc Duplex Steel 2205: Micromechanical Testing and Nanoindentation Examination of Hardness Variations
Study of Neutron Irradiation Damage of HT-UPS Steel Using Synchrotron X-ray Techniques
Study of Niobium Clustering in Zr-1.0%Nb Alloy Irradiated with Kr2+ Ions or Neutrons to ~9 dpa at 310 °C
Suppressing Void Swelling in NiCoFeCr-based High Entropy Alloys via Selective Doping
The Effect of Point Defects on the Thermodynamics and Kinetics of Irradiated Materials
Three Dimensional Radiation Effects in Neutron Irradiated Uranium-Molybdenum Fuel
Three Dimensional Rate Theory Models of Radiation Damage with Mechanical Fields
Understanding the Effect of Gamma Radiation on the Corrosion of Zirconium Alloys

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