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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Characterization of Stress and Environment Dependent Fracture Mechanisms of SiC/SiC CMCs
Author(s) Morgan Claire Price, Clifton Bumgardner, Frederick Heim, David Roache, Xiaodong Li
On-Site Speaker (Planned) Morgan Claire Price
Abstract Scope Silicon carbide fiber reinforced silicon carbide matrix (SiC/SiC CMCs) composites, which are used in nuclear reactor applications for superior high temperature and corrosion resistant properties, exhibit degraded mechanical strength and embrittlement under sustained or slowly ramping stress levels. The morphology and distribution of microcracks was evaluated during tension and expanding plug tests with variable strain rates and levels of environmental exposure (up to 1200 C in inert and oxidizing environments). All tests were conducted with in-situ monitoring of local deformation using stereoscopic digital image correlation and acoustic emissions to characterize microcrack growth. Experimental crack growth mechanisms, including crack opening displacement with stress level, were used to validate a finite element model to predict the fracture energy release. Thus, this study aims to elucidate the coupled stress-based and environmental-based mechanisms driving crack initiation and propagation within SiC/SiC composites.
Proceedings Inclusion? Planned: Publication outside of MS&T

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
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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
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Unveiling High Temperature Damage Mechanisms via In-situ Digital Image Correlation of Chromium-coated Zirconium-based Fuel Claddings

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