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Meeting 2018 TMS Annual Meeting & Exhibition
Symposium Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
Presentation Title Irradiation Temperature Influence on Nanolayered Response in Select MAX Phase Ceramics to High Fluence Self-ion Irradiation
Author(s) William Alexander Hanson, William J Weber, Yanwen Zhang
On-Site Speaker (Planned) William Alexander Hanson
Abstract Scope To expand energy production capacity, next generation fission and fusion reactors will require materials to withstand more hostile temperatures and irradiation conditions. The high thermal conductivity and stability of Mn+1AXn phases has led to irradiation studies of Ti3SiC2, which demonstrates an apparent resistance to radiation-induced structural damage. However, debate in the community over the source of TiC impurity concentration changes demands a need for better understanding of the structural response of the nanolaminate A-layer to irradiation. Therefore, room and elevated temperature 9 MeV Ti3+ self-ion irradiations were performed at the University of Tennessee Ion Beam Materials Laboratory to fluences of 2.8E16, 3.5E16, and 4.2E16 ion/cm2, and microstructural changes with depth were measured utilizing grazing incidence x-ray diffraction and transmission electron microscopy. The results reveal that the TiC concentration apparently increases near the surface where electronic stopping dominates, suggesting it may play a more important role than previously believed.
Proceedings Inclusion? Planned: Supplemental Proceedings volume


3D Study of Neutron-irradiated Fe-9Cr Alloy and 316 Stainless Steel Using Far-field and Near-field High-energy X-ray Diffraction Microscopy
A Heterogeneous Cavity Nucleation Model for Swelling in Simulated Ferritic Alloys
Accelerated Materials Evaluation of Damage Mechanisms in Concentrated Solid Solution Alloys
Atomistically-informed Cluster Dynamics Modeling of Defect Cluster Evolution in Irradiated Structural Materials
Carbon Contamination in Ferritic/Martensitic Steels during Ion Irradiation: Characterization and Mitigation
Characterizing Displacement Cascade Damage via Virtual Diffraction Techniques
Characterizing the Defect Structure and Defect Density in Neutron and Proton Irradiated Zr Alloys by X-ray Line Profile Analysis
Deconvolution of Complex Environmental Effects Active in Nuclear Reactor Materials Through In-situ Ion Irradiation
Dislocation Loop Formation in Proton Irradiated Pure Zirconium
Effect of Alloying Elements on Defect Evolution in Ni-20X Concentrated Binary Alloys
Effect of Friction Stir Welding on Microstructure Evolution on In Situ and Ex Situ Self-ion Irradiated MA956
Effect of Irradiation Dose Rate on Precipitation in Fe-Cu and Fe-Cu-Mn Model Alloys
Effect of Temperature and Helium on Microstructure Evolution in Dual Ion Irradiated HT9 Steel
Enhanced Dynamic Recovery of Radiation Damage in Silicon Carbide under Accelerated Testing Using Ion Beams
F-10: Swelling Quantification of High Dose Helium Implantation in Different Materials Using a Helium Ion Beam Microscope
F-11: The Role of Oxides in Nanostructured Ferritic Alloys and Fe-Y2Ti2O7 Bilayers: Interfaces, Helium Partitioning and Bubble Formation
F-1: Current Status of In-situ Tritium Measurements from TMIST-3A
F-2: Dose Effect on the Irradiation Induced Loop Density and Burgers Vector in Ion-irradiated Alloy T91 Irradiated In-situ in a TEM
F-3: Grain Boundary Influence on Displacement Cascades in ZrC
F-4: In Situ TEM Study on the Radiation Response of Nanotwinned-nanovoid Cu
F-5: Investigation of Helium-Defect Interactions in Tungsten through Coordinated Modeling and Experiment
F-6: Irradiation Response of Twin Boundaries in Face-centered Cubic Metals with Low Stacking Fault Energy
F-7: Radiation Response in Single-phase Concentrated Solid Solution Alloys
F-8: Self-organization of Helium Precipitates into Elongated Channels within Metal Nano-layers
F-9: Studying the Influence of In Situ Proton Irradiation on Corrosion in Molten Salt
High-dose Neutron Irradiation Induced Evolution of Mechanical Properties and Microstructure of Ferritic/Martensitic Steels
Impact of Irradiation-Enhanced Diffusion on Implanted Ion Profiles
Impact of Temperature on Microstructural Features using Dual Ion-irradiation in T91 Steel
Ion and Neutron Irradiation Effects in a Co-free High Entropy Alloy
Irradiation Temperature Influence on Nanolayered Response in Select MAX Phase Ceramics to High Fluence Self-ion Irradiation
Linking RIS and Grain Decohesion Using In Situ TEM 4-point Beams
Localized Helium Implantation Utilizing a Helium Ion Beam Microscope to Evaluate Swelling and Mechanical Property Changes
Mechanical Properties, Damage and Morphology Details of Nanocrystalline and Ultrafine Tungsten Materials Exposed to Low Energy Helium and Heavy Ion Irradiation
Microstructural and Nanoindentation Properties of a Lanthanum-containing Nanostructured Ferritic Steel Irradiated by High Dose Iron Ions
Microstructural Characterization of the Processes, Stability, and End-of-range Effects in Heavily Irradiated Pyrochlores
Microstructural Evaluation of Ion Irradiated Model Binary Alloys
Microstructural Investigations of Temperature Effects in Reactor Pressure Vessel Steels from the UCSB ATR-2 Irradiation
Microstructure Evolution in BOR60 Irradiated T91
Modeling and Validation on Role of Stoichiometry on Degradation in Ni-Cr Alloys for Nuclear Applications
Neutron Re-irradiation and Neutron-ion Irradiation Bootstrapping Approaches to Study Very High Dpa and He Effects in Nuclear Materials
Quantifying Radiation Damage in Materials Using Stored Energy Fingerprints
Self-Organization of Gas Bubble Superlattices
Simulation and Experimental Investigation on the Applications of Nonlinear Ultrasonic Techniques in Non-destructive Probes of Nuclear Materials
Simulation of Impact Toughness with the Effect of Temperature and Irradiation in Steels
Structural Damage and Phase Stability of Al0.3CoCrFeNi High Entropy Alloy under High Temperature Ion Irradiation
TEM with In Situ Ion Irradiation of Nuclear Materials at the IVEM-tandem
Temperature Shift for Emulating Solute Cluster Evolution Using Higher Dose Rate Irradiation
The Influence of Bimodal Cavity Distributions on Swelling Evolution in Helium Pre-implanted T91
The Structure and Composition of Mn-Ni-Si Precipitates in an Irradiated High-Ni RPV Steel Following Aging at 425C for 57 Weeks
Towards In-situ Thermo-mechanical Property Monitoring during Ion Irradiation
Using Ion Irradiation to Extend the Damage Level of Neutron Irradiated 304L Stainless Steel
Void Swelling Evolution and Radiation-induced Segregation & Precipitation in Self-ion Irradiated Ferritic/Martensitic HT9 Steel

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