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Meeting 2015 TMS Annual Meeting & Exhibition
Symposium Microstructural Processes in Irradiated Materials
Sponsorship TMS: Nuclear Materials Committee
Organizer(s) Dane Morgan, University of Wisconsin - Madison
Thak Sang Byun, Oak Ridge National Laboratory
Yasuyoshi Nagai, Tohoku University
Zhijie Jiao, University of Michigan
Kai Nordlund, University of Helsinki
Ming-Jie Zheng, University of Wisconsin
Scope Radiation can produce significant degradation in the properties of materials. An understanding of the microstructural changes occurring during irradiation is critical for the development of advanced materials as well as for modeling property changes. The scope of this symposium will focus on the microstructural changes occurring in solids during ion, electron, neutron, gamma ray or x-ray irradiation. This symposium, which is the 7th in a series of symposia held every two years since 2003, is intended to bring together researchers working on different materials systems and radiation induced phenomena so that similarities and differences in radiation effects can be compared and integrated. Materials of interest include all nuclear structural, fuel, and functional materials. Both experimental and theoretical studies are solicited with a particular emphasis on linking state-of-the-art modeling with experimental observation of materials microstructure and property evolution.

Specific topics where contributions are encouraged include:

- Defect generation, evolution and characterization
- Radiation induced precipitation, amorphization, and recrystallization
- In-situ studies of dislocation–radiation defect interactions
- Phase stability, segregation, and diffusion
- Radiation damage in fusion & fission reactor materials
- Mechanisms of deformation and fracture in irradiated materials
- Radiation effects simulation and evaluation techniques
- Integrated phenomena in reactor core materials
- Microstructural changes in metallic and ceramic fuels
- Advanced ODS steels, austenitic and ferritic-martensitic steels
- Refractory metals, carbon and ceramic materials
Abstracts Due 07/15/2014
Proceedings Plan Planned: A print-only volume

A New Self-Healing Paradigm of Radiation Damage: Grain Boundary Bulging and Recovery
An Investigation of the Applied Stress Effect on Void Swelling Behavior of Polycrystalline Stainless Steel Using Phase-Field Method
Anomalous Defect Evolution in Irradiated UHP Tungsten: In Situ TEM Observations and Interpretation
APT Investigation of the Effect of Neutron Fluence on the Microstructural Evolution of Irradiated Low Copper RPV Steels
Direct Observation and Interpretation of Helium Implantation Effect on Microstructure and physical Properties of Plasma-Facing Fusion Materials
Effect of Point Defect Sinks on Irradiation Induced Compositional Patterning
Effects of Dose Rate and Primary Defect Structure on Microstructural Evolutions in RPV Steels
Experimental Approach to Determine the Barrier Strength Factor for Mobile Dislocation against Void and He Bubble in ion-Irradiated Mo
Heavy Ion Irradiation on Ultrafine-and Nanocrystalline-Grained Tungsten: Effect of 3 MeV Si, Cu and W Ions
Initiation of Nanostructure Formation on Tungsten Irradiated with 30 keV Helium Ions
Ionization-Induced Self-Healing of Ballistic Collision Damage in Silicon Carbide
Neutron Irradiation Effects on Microstructural Development of Tungsten and Tungsten Alloys
Simulation of Xenon, Uranium Vacancy and Uranium Interstitial Diffusion and Grain Boundary Segregation in UO2
Structural Characterization of Nano-Precipitates in Irradiated Reactor Pressure Vessel Steels
A TEM Study of the Effect of Neutron Irradiation on the Microstructure of Fe-Cr Alloys
Ab Initio Investigation of He Bubbles at the Y2Ti2O7-Fe Interface in Nanostructured Ferritic Alloys
Ab Initio Study for Resistance to Radiation-Induced Amorphization in ZrC
An Overview of Selected Results from LONGLIFE and PERFORM60 European Projects
Atom Probe Tomography Characterizations of Irradiated and Annealed Reactor Pressure Vessel Surveillance Specimens
C21: Charged Particle Irradiation Studies of High Dose Precipitation in Reactor Pressure Vessel Steels
C22: Low Dose Proton Irradiation Creep of FM Steel T91
C25: Segregation Behaviour of Transmutation Elements Ca, Ti, Sc in the F82H Steel Irradiated under Mixed Spectrum Irradiation of High Energy Protons and Spallation Neutrons
C26: Swelling, Grain Stability and Hardness Changes of Several Variants of Ferritic Alloy EK-181 at Doses of 100 to 600 dpa during Self Ion Irradiation
C27: Microstructure and Mechanical Property Evolution during Tube Processing of Oxide Dispersion Strengthened (ODS) Ferritic Steels
C28: KMC Modeling of Helium Bubble Clustering and Evolution in BCC Iron
C29: Effects of Co-Injected Helium on the Irradiated Microstructure in Ion-Irradiated T91 Steel
C31: The Strengthening Mechanism Transition in Nanofeatured Ferritic-Martensitic Alloys
C32: Incubation Dose for Void Swelling in Ferritic-Martensitic Steels
C33: APT and TEM Investigation of the Evolution of the Microstructure of Ion Irradiated ODS Ferritic Steels
C34: Characterization of Developed Microstructure of Nanocrystalline Copper Post Neutron and Ion Irradiation
C35: Grain Boundary Distribution Effects in Ni Alloys
C36: Evaluation of Radiation Effects in FeMnNiCr High Entropy Alloy
C37: Analysis of Stress Corrosion Crack Initiation in Neutron-Irradiated 304 Stainless Steel Tested in Simulated PWR Environment
C38: Irradiation-Induced Nanoprecipitation in Ni-W Alloys
C39: Temperature and Irradiation Species Dependence of Radiation Response of Nanocrystalline Silicon Carbide
C40: Damage Evolution in Irradiated SiC: Modeling and Experimental Study
C41: Evolution of Black Spots Defects and Small Clusters in Irradiated 3C-SiC
C42: Irradiation Effects on Fission Product Diffusion in SiC
C43: Radiation-Enhanced Impurity and Self-Diffusion in Nitrides by Atomistic Study
C44: Ion Irradiation Induced Defects in Boron Carbide
C45: Atomistic Characterization of Uranium Vacancy Interaction with External Strains and Dislocations in Uranium Dioxide
C46: Thermal Boundary Resistance and Irradiation Effects of the Grain Boundaries in Ceria
C47: Short-Range Atomic Order in Ion-Tracks in Pyrochlores
C49: Stability of Nanocluster and Nanoparticle Systems Embedded in Dielectric Substrates
C51: Self-Irradiation Effects on Metallurgical Properties of Plutonium Alloys
C52: Ion-Beam Irradiation Assisted Microstructure Control in Refractory Metal Films
C53: Modelling Void Swelling Suppression by Injected Interstitials and Free Surfaces in Ion Irradiation
C54: Real Time and In Situ Studies of Materials in a Radiation Environment (MRE)
C55: Effects of Neutron and Ion Irradiation on Zr52.5Cu17.9Ni14.6Al10Ti5 (BAM-11) Bulk Metallic Glass
C56: Some Remarks on In-Situ Studies Using TEM-Heavy-Ion Accelerator Link from the Stand Point of Extracting Radiation Damage Caused by Fast Neutrons
C57: Atomic Scale Details of Defect-Boundary Interactions
C58: Examination of Uncertainty in Kinetic Monte Carlo Simulations of bcc Metals
Characterization of Mesoscopic Fe - {111}, {110} and {100} Y2Ti2O7 Interfaces
Cluster Dynamics Modeling of Irradiation Induced Defects in Ferritic Alloys
Cluster Dynamics Modeling of Multi-Phase Mn-Ni-Si-Rich Precipitation Evolution in Low Cu RPV Steels
Constitutive Modeling of Irradiation Effect on Silicon Carbide Composites
Depth-Dependence of Ion-Induced Swelling in Ferritic-Martensitic ODS Alloys
Development of Combined Thermomechanical and Radiation Testing Platforms
Development of Improved Accident Tolerant Cladding Materials
Diffusivity and Solubility of Cu in Fe and A533B Measured by Atom Probe Tomography
Disordering and Dissolution of Ordered L12 Precipitate in Rene N4 under Irradiation
Dynamical Phase Diagrams under Irradiation
Effect of Cu and Mn on Radiation Induced Hardening and Microstructure of A533B Model Alloys
Effects of Chemical Disorder on Defect Dynamics under Ion Irradiation
Effects of Radiation in Silicon Carbide Ceramics and Composites: Current Understanding of Irradiation Stability and Our Ability to Characterize Irradiation-Induced Miscrostructural Evolution
Energetic Study of Helium Bubble Formation in Y-Ti-O Enriched Iron Matrix
Ferrite Decomposition and G-Phase Precipitation in Ion-Irradiated CASS CF8 Revealed by APT
Improved Swelling Resistance of ODS Alloys by Combining the Swelling Resistance Arising from both Dispersoids and Tempered Martensite Phase
Improvement of Irradiation and Corrosion Resistance of a 316 Austenitic Stainless Steel by Grain Refinement
In Situ Observation of Defect Annihilation in Kr Ion Irradiated Bulk Fe/Fe2Zr Nanocomposite Alloy
Influence of Electronic Stopping on Radiation-Induced Defect Formation in Iron
Influence of Grain Boundary Character Effects in Neutron Irradiated Stainless Steel
Influence of Irradiation Induced Point Defects on Thermal Conductivity in UO2
Investigation of bcc-Fe Interfaces with B2 Intermetallic Alloys
Investigation of Microstructural Evolution in Cu-W and Cu-Ni-W Systems under Irradiation Using In-Situ Electrical Resistivity Measurements and Electron Microscopy
Ion Irradiation Characterization Studies of MAX Phase Ceramics
Irradiation Effects in Oxide Nanoparticle Stability in Oxide Dispersion Strengthened (ODS) Steel
Issues Concerning Neutron-Atypical Artifacts Introduced by Ion Irradiation Experiments for Simulation of Neutron Irradiation of Pure Iron (Was Poster C-30)
Measuring and Modeling Defect Formation and Kinetics in Ion Irradiated Mo at 30 K and 300 C in the Recently Reopened IVEM-Tandem Facility
Mesoscale Modeling of Effects of Radiation-Induced Microstructures on Thermal Transport in UO2
Microstructures and Helium Ion Implantation Effects in HIPed and SPSed 9Cr-ODS Steels
Modeling Gas Bubble Evolution on Grain Boundaries under Irradiation
Modeling Radiation Damage in Bulk Tungsten under Fusion Conditions
Multiscale Simulations of Strengthening Induced by Radiation-Induced Cr Precipitates
Neutron Flux Effects on Irradiation-Induced Solute Clusters and Matrix Defects in RPV Steels Studied by Positron Annihilation
On The Effects of Helium-dpa Interactions on Cavity Evolutions in Tempered Martensitic Steels: Analyses of Dual Ion Irradiations Data
Optimum Size Effect to Achieve Enhanced Radiation Tolerance in Immiscible Cu/Fe Multilayers
Overview on the Fracture Behavior of High Chromium Ferritic-Martensitic and Nanostructured Ferritic Alloys
Phase Instability in 300 Series Austenitic Steels Irradiated in Different Environments
Physics-Based Modeling of Zirconium Hydride Precipitation and Growth in Zirconium Using a CALPHAD-Based Phase Field Model
Precipitation Evolution in HT9 at High Dose
Progress on Understanding Helium-Displacement Damage Interaction Effects on Void Swelling in Tempered Martensitic Steels
Quantitative Characterization of Microstructures in Proton Irradiated Stainless Steels
Radiation-Induced Segregation at High Doses in Self-Ion Irradiated F/M Alloys
Radiation Response of Nanolayered, Nanoporous and Nanotwinned Metals
Role of Alloy Variation on Swelling Behavior in Self-Ion Irradiated Ferritic-Martensitic Steel
Role of Interfaces in Trapping Implanted He in Two-Dimensional and Three-Dimensional Cu/Nb Nanocomposites
Strength Factor of Voids and He Bubbles in BCC Fe
Strengthening Mechanisms Due to Hard Obstacles in Ferritic Alloys.
Structure and Kinetics of “Invisible” Defects in Irradiated SiC
Swelling and Radiation-Induced Segregation/Depletion in Annealed 304SS Irradiated at PWR-Relevant Dose Rates
TEM Study of Restructuring of LWR UO2 Fuels at Very High Burnup
The Capillarity Equation at the Nanoscale: He Trapping at Grain Boundaries
The Effect of Fe on Dislocation Loop Formation Studied in Pproton-Irradiated Binary Zr Alloys
Thermal Stability of Nanoscale Ni-Mn-Si Precipitates in Irradiated Reactor Pressure Vessel Steels
Vacancy Clustering in Zirconium: An Atomic Scale Study
Void Swelling Behavior in High Dose Ion Irradiated Ferritic-Martensitic Steels

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