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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Analysis of Heavy Ion Irradiation Damage in Commercially Pure Titanium and Titanium Alloys
Author(s) Aida Amroussia, Carl J Boehlert, Frederique Pellemoine, Wolfgang Mittig, David S Grummon, Thomas Bieler, Clara Grygiel, Meimei Li, Wei-Ying Chen, Isabelle Monnet
On-Site Speaker (Planned) Aida Amroussia
Abstract Scope Thanks to their good mechanical properties and low activation under irradiation, titanium alloys are selected for several applications in radioactive environments. The current study investigated the effect of ion irradiation damage on the microstructure and the nano-hardness in Ti and Ti alloys, namely commercially pure (CP) Ti and a two-phase α+β Ti-6Al-4V (wt.%) alloy processed through conventional powder metallurgy rolling (PM) and additive manufacturing (AM). Radiation hardening was observed in all materials irradiated ex situ at 30℃ and 360℃. A strong dose dependence was observed especially for the PM α+β Ti-alloy. The resistance to radiation hardening in the AM Ti-alloy was higher than that for the PM rolled alloy due to its lamellar microstructure. The radiation-induced dislocation loop evolution was investigated through in situ TEM irradiation at different temperatures in Ti and AM Ti-6Al-4V. The dispersed barrier hardening model was successfully used to analyze structure-mechanics relationships in irradiated CP Ti.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

In Situ Observation of Short- and Long-Timescale Material Property Evolution Under Extreme Conditions
Analysis of Heavy Ion Irradiation Damage in Commercially Pure Titanium and Titanium Alloys
Benefits of Using High Energy Ions in Ion Irradiation Experiments to Evaluate Void Swelling
Characterization of Microstructure Evolution in Ceramic Materials Using Acoustic and Thermal Transport Measurements
Characterization of Stress and Environment Dependent Fracture Mechanisms of SiC/SiC CMCs
Controlling Helium Morphology in Pure Metals: Effects of Helium Defects on Deformation and Strength
Corrosion Control of Austenitic Stainless Steel and Nickel-Based Alloys in Molten Chloride Salt Environments
Design of a Hot Hydrogen Test Loop for Testing of Nuclear Thermal Rocket Elements
Development of a Combined Thermal Hydraulic and Materials Corrosion Liquid-Sodium Experimental Facility
Development of an In-Situ Mechanical Test System for Advanced Reactor Coolants
Effects of Post-Processing Variability on Radiation Response of Additively-Manufactured HT9
Enabling In-situ Crack Growth Testing and Monitoring in VTR Cartridge Loop Environments
Explaining the Corrosion Morphology of Structural Materials in Molten Fluoride Salts With/Without Radiation
Fundamental In-situ Experiments Coupled to High-throughput Approaches to Understand Radiation Damage in FCC and BCC Compositionally Complex Alloys
In situ Crack Loading and Measurement Techniques for Gen IV Reactor Coolant Media
In Situ Observation of Irradiation Damage in Polycrystalline Nuclear Graphite
Investigation of Uranium Silicide Fuel Form Additions through Rietveld Refinement and Internal Standard P-XRD
Mobility of Hydrogen in YH2 Probed by Nuclear Magnetic Resonance
Modified stereo TEM for 3D analysis of defects
Nanomechanical Change of Tungsten in ELM Conditions
Nonlinear Ultrasound for Nondestructive Evaluation of Microstructural Defects
Response of an Additively Manufactured 316 Stainless Steel Subjected to High Temperature Heavy Ion Irradiations
Selective Irradiation Behavior in Dual Phase 308L Filler of SA508-304L Dissimilar Metal Weldment after Proton Irradiation
STEM Characterization of Dislocation Loops for an Irradiated Model FCC Alloy
Study on Hydrogen Isotopes Solubility and Diffusivity in Y- and Co-doped Barium-zirconates Using Tritium Imaging Plate Technique
Swelling of Nuclear Reactor Steels: Modeling, Theory, and Accelerated Testing
Unveiling High Temperature Damage Mechanisms via In-situ Digital Image Correlation of Chromium-coated Zirconium-based Fuel Claddings
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