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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Sponsorship TMS Nuclear Materials Committee
Organizer(s) Samuel A. Briggs, Oregon State University
Christopher M. Barr, Department Of Energy
Emily Aradi, University of Huddersfield
Michael Philip Short, Massachusetts Institute of Technology
Janelle P. Wharry, Purdue University
Cheng Sun, Clemson University
Dong Liu, University of Oxford
Khalid Hattar, University of Tennessee Knoxville
Scope In the last decade a wealth of new analytical and in-situ experimental tools has emerged, increasing the speed and fidelity with which microstructural evolution can be characterized. This symposium solicits presentations that apply any of these advanced techniques to the study of materials structure, properties, and performance in radiation and other extreme environments, e.g. nuclear energy and space applications. These technique advancements have occurred in areas including microstructural characterization, thermophysical property measurement, in situ measurements, and small-scale mechanical property testing. There is a specific interest in techniques that directly impact materials research for environments exhibiting high radiation fields, extreme temperatures, and corrosive or chemically-reactive environments. The unique data provided by these advanced characterization tools also provide a new bridge to enhance the framing, refining, and validation of predictive models.

Specific topics include, but are not limited to:
-Novel (destructive and non-destructive) techniques for characterization radiation damage
-Non-contact thermal and elastic measurement techniques
-Mechanical behavior – emphasis on small scale testing (SEM or TEM length scales)
-Direct observation of radiation-induced microstructural transformations in real time
-Methods for monitoring corrosive attack in non-aqueous coolant environments
-Studies of synergistic effects of these superimposed extreme environments relating to materials degradation
-Work enabling enhanced coupling of experimental results with predictive modeling and simulation

Abstracts Due 05/31/2020
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

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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