ProgramMaster Logo
Conference Tools for 2018 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2018 TMS Annual Meeting & Exhibition
Symposium Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
Presentation Title Microstructural and Nanoindentation Properties of a Lanthanum-containing Nanostructured Ferritic Steel Irradiated by High Dose Iron Ions
Author(s) Somayeh Pasebani, Indrajit Charit, Yaqiao Wu, Jatuporn Burns, Darryl P. Butt, James I. Cole, Lin Shao
On-Site Speaker (Planned) Somayeh Pasebani
Abstract Scope A nanostructured ferritic steel with a nominal composition of Fe-14Cr-1Ti-0.3Mo-0.5La2O3 (wt.%) was irradiated with Fe+2 ions at 475C for 100, 200, 300 and 400 dpa. Grain coarsening was observed for the samples irradiated for 200-400 dpa with an increase in the average grain size from 152 nm to 620 nm likely due to the coarsening of Cr-O rich nanoparticles (NPs). Dislocation density consistently increased with increasing irradiation dose at 300 and 400 dpa. The mean radius of lanthanum-containing nanoclusters (NCs) decreased and their number density increased above 200 dpa, which is likely due to solutes ejection caused by ballistic dissolution and irradiation-enhanced diffusion. Chromium, titanium, oxygen and lanthanum content of nanoclusters irradiated at 200 dpa and higher got reduced by almost half the initial value. The reduction nanocluster size accompanied with their higher number density and higher dislocation density led to significant radiation hardening with increasing radiation doses.
Proceedings Inclusion? Planned: Supplemental Proceedings volume

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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 Advanced Nuclear Materials Development at LAMDA through the NSUF Mechanism
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
Current Status of In-situ Tritium Measurements from TMIST-3A
Deconvolution of Complex Environmental Effects Active in Nuclear Reactor Materials Through In-situ Ion Irradiation
Dislocation Loop Formation in Proton Irradiated Pure Zirconium
Dose Effect on the Irradiation Induced Loop Density and Burgers Vector in Ion-irradiated Alloy T91 Irradiated In-situ in a TEM
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
Grain Boundary Influence on Displacement Cascades in ZrC
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
In Situ TEM study on the Radiation Response of Nanotwinned-nanovoid Cu
Investigation of Helium-Defect Interactions in Tungsten through Coordinated Modeling and Experiment
Ion and Neutron Irradiation Effects in a Co-free High Entropy Alloy
Irradiation Response of Twin Boundaries in Face-centered Cubic Metals with Low Stacking Fault Energy
Irradiation Responses of Ultrastrong Nano Precipitation Martensite Steel at Elevated Temperatures
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
Radiation Response in Single-phase Concentrated Solid Solution Alloys
Self-Organization of Gas Bubble Superlattices
Self-organization of Helium Precipitates into Elongated Channels within Metal Nano-layers
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
Studying the Influence of In Situ Proton Irradiation on Corrosion in Molten Salt
Swelling Quantification of High Dose Helium Implantation in Different Materials Using a Helium Ion Beam Microscope
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 Role of Oxides in Nanostructured Ferritic Alloys and Fe-Y2Ti2O7 Bilayers: Interfaces, Helium Partitioning and Bubble Formation
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

Questions about ProgramMaster? Contact programming@programmaster.org