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Meeting 2014 TMS Annual Meeting & Exhibition
Symposium Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Modeling
Sponsorship TMS Structural Materials Division
TMS/ASM: Nuclear Materials Committee
Organizer(s) Peter Hosemann, University of California, Berkeley
Julie D. Tucker, Oregon State University
James I Cole, Idaho National Laboratory
Todd R. Allen, Idaho National Laboratory
Scope The response of fuels and materials to radiation is critical to the performance of advanced nuclear systems. Key to understand material performance in a nuclear environment is the analysis of materials irradiated using test reactors and ion beam facilities. This symposium will focus on recent results produced from irradiation programs around the world and will cover fundamental and applied science aspects of accelerated nuclear materials testing for fission and fusion reactors. Presentations combining experiment with theory, modeling and simulation to enhance our understanding of radiation induced degradation in materials are especially encouraged. Abstracts are solicited in (but not limited to) the following topics:

Fundamental science of radiation damage and defect processes
Mechanical and fracture behavior of irradiated materials
Current and advanced nuclear fuels
Current and advanced structural materials
Ion irradiation effects in materials
Abstracts Due 07/15/2013
Proceedings Plan Planned: A print-only volume

A First-principles Model for the Effect of He Damage on Mechanical Properties of Tungsten Alloys
Advanced Nuclear Fuel Concepts for Minor Actinide Burning
Behavior of Fe-Cr alloys under Ion or Neutron Irradiation
Calculation of Displacement Doses for Ion Beam Simulation of Neutron Damage in Metals and Structural Alloys
Characterization of Radiation Damage Tolerant Cu/Nb Nanocomposites Using Synchrotron Based X-ray Methods and Transmission Electron Microscopy
Combined First-principle and CALPHAD Modeling of Multi-phase Mn-Ni-Si-rich Precipitation in RPV Steels
Contribution from Anisotropic Dislocation Loop Distribution to Irradiation Creep of F-M Steel T91
Corrosion and Hydrogen Pickup of Zircaloy-4 in Simulated PWR Environments with In-situ Proton Irradiation
Corrosion of 316L Stainless Steel in Simulated PWR Conditions with In-situ Proton Irradiation
Effect of Neutron Irradiation on Select Mn+1AXn Phases
Effects of Strain on Damage Generation in bcc Fe
Emulation of High Dose Reactor Irradiations of F-M Alloys Using Self-Ions
Evolution of the ATR NSUF in Supporting Nuclear Fuels and Materials R&D
Grain Boundary Structure Effects on Radiation Induced Segregation in Neutron Irradiated Type 304 Stainless Steels Variants
Grain Orientation Dependence of Deformation Twinning in Irradiated and Nonirradiated Austenitic Stainless Steels
Heavy Ion Irradiations of Fe-Cr Binary Alloys
Helium Behaviour in Ferritic/Martensitic Steels Irradiated in a Spallation Target and Implanted with Helium
High-Dose Void Swelling in Ion-Irradiated Ferritic-Martensitic Steels
Impact of Beam Rastering on Void Swelling in Pure Iron
Implantation and Characterization of Helium in Nuclear Materials at Jannus-Saclay (France)
In Situ Measurement of Heavy-ion-irradiation-induced Plastic Flow of Amorphous CuTiAg Micropillars
In Situ SEM Characterization of Irradiated Stainless Steel
Influence of Proton Irradiation on the Precipitation Kinetics and Mechanical Properties of an Intermetallic Precipitation Hardened Steel
Ion Beam Experiment to Simulate Simultaneous Molten Salt Corrosion and Fast Neutron Damage for Advanced Fuel Cycles
Ion Irradiation Effects on Model FE-CR Alloys
Ion Irradiation Effects on Nanocluster Precipitation in Steels
Irradiation Damage Development in Zirconium Carbide
Irradiation Effects in Aged Cast Duplex Stainless Steels
L10: Effect of Heavy Ion Irradiation on Microstructural Evolution in CF8 Cast Austenitic Stainless Steel
L12: Effect of Low Dose Neutron Irradiation on Tensile Behavior of HT-9 Steel at Room Temperature
L13: Effect of Radiation-induced Lattice Defects on Precipitate Formation in Dilute Fe-Cu-Ni Alloy
L14: Effects of Dose Rate and Primary Defect Structure on Microstructural Evolution in RPV Steels
L15: Effects of Proton Irradiation and Helium Implantation in Al/B4C MMC for Spent Nuclear Fuel Storage
L16: Exploring Fission Enhanced Diffusion of Uranium in Uranium Dioxide Using Classical Molecular Dynamics Simulations
L17: Helium Implantation Effects on the Tensile Properties and Microstructure of Amorphous Nickel Phosphorous
L18: High Temperature Nanoindentation on Nanostructured Materials
L1: An Electron Energy Loss Spectroscopy Study of Helium Bubbles in Nanostructured Ferritic Alloys
L20: Impact of the Injected Interstitial Effect on Ion-induced Void Swelling in Austenitic and Ferritic-martensitic Alloys
L21: Influences of the Injected Interstitial and Defect Imbalance on Void Swelling of Pure Iron at 450C
L22: Ion-induced Swelling of Yttrium Oxide Dispersion-strengthened 0Cr18Ni10Ti Steel
L23: Irradiation Studies on Friction Stir Welded Oxide Dispersion Strengthened Alloys
L24: Local Chromium Enrichments in High Dose Irradiated Oxide Dispersion Strengthened Steel Alloys
L26: Microstructure Analysis of Ion Beam Irradiated CNS-I and CNS-II Steels
L27: Molecular Dynamics Simulations of Displacement Cascades in BCC Metals
L28: Real Time and In Situ Studies of Materials in a Radiation Environment (MRE)
L29: Removal of Defect Clusters by Twin Boundaries in Nanotwinned Metals
L30: Role of Beam Rastering on Microstructural Evolution in Ion Irradiated HT9 Steel
L31: Self-interstitial Diffusion in Concentrated Fe-Cr by Kinetic Monte Carlo and First Principle Molecular Dynamics Simulations.
L32: Simulation of Radiation Damage of Zirconium Alloys with Accelerator of Heavy Ions
L33: Stability of Interfaces in Thin Film-substrate System under Ion Irradiation
L34: Study of Radiation-induced Segregation Using Nickel-chromium Binary Alloys
L35: Study of Xe Ion Beam Irradiated Mo Single Crystal by Synchrotron Extended X-ray Absorption Fine Structure
L36: Surface Stabilities and Helium Trapping of Nano-sized Oxide Phases in Nano-structured Ferritic Alloys: A First Principles Study
L37: Ultrasonic Signatures of Degradation in Advanced Reactor Materials
L4: Cluster Dynamics Modeling of Defect Cluster Evolution in Ion Irradiated Epitaxial Cr Films on MgO
L6: Comparative Mechanical Properties Analysis of Ion Irradiated Potential Nuclear Fusion Candidate Materials
L7: Comparison of Microstructure of Ion-irradiated and Neutron-irradiated Tubing Made from MA957 ODS Ferritic Alloy
L9: Deformation Behavior of Ion Irradiated Zr-4 Cladding Material: Comparison of Experiments to Modeling
Mechanism of Irradiation-induced Creep in Ultra-fine Grain Graphite
Microstructural Characterization of Test Reactor Irradiated RPV Steels by Post-irradiation Annealing and State-of-the-art Characterization Tools
Microstructure and Mechanical Property Studies on Neutron-irradiated Ferritic FeCr Model Alloys
Modeling the Effect of Irradiation on Plasticity and Creep in Zr and Zircoloy
Multiscale Modeling of Defect Cluster Evolution in Irradiated Structural Materials
Novel View of the Effect of Crystal Lattice on Novel View of the Effect of Crystal Lattice on Microstructure Evolution in Irradiated Metallic Materials
On the Opportunities and Challenges for Using Test Reactor and Charged Particle Irradiations to Help Predict Inaccessible In-service Neutron Irradiations Effects
Peculiarities of Ion Beam Irradiation Studies
Phase Stability and Evolution of Ion-irradiated Uranium-rich Alloys for Advanced Nuclear Fuels
Radiation-induced Microstructure in Metallic Nanopillars
Radiation Response of Silicon Carbide under In-situ Electron Irradiation
Relaxation Time of Transient Radiation Induced Defects
The Effect of External Stress on Ion Irradiation-induced c-Loop Formation in Zry-4
Tuning Ideal Tensile Strengths and Intrinsic Ductility of BCC Refractory Alloys
Use of In-situ TEM to Study the Response of Metallic Systems Under Ion-beam Irradiation
Viability of SiC/SiC Composites as LWR Cladding: Bridging Experiments and Fuel Performance Modeling
What Have We Learned from Ion Bombardment Studies to Allow Development of Improved Swelling-resistant Ferritic-martensitic and ODS Alloys for Service to Very High Neutron Fluence?

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