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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Selective Irradiation Behavior in Dual Phase 308L Filler of SA508-304L Dissimilar Metal Weldment after Proton Irradiation
Author(s) Zhen Li, Xun Zhan, Weicheng Zhong, Benjamin Sutton, Ovidiu Toader, Gary Was, Brent Heuser
On-Site Speaker (Planned) Zhen Li
Abstract Scope Selective irradiation behaviors in mixed phase 308L filler of 508-304 DWM after proton irradiation were investigated to a depth of 0 to 10 Ám. Ni-Si-Mn enriched precipitates were observed under SEM and TEM in δ ferrite, which is possibly attributed to the much higher diffusivity of solute elements in δ ferrite. STEM-EDS, TEM dark field imaging and diffraction patterns confirmed that these Ni-Si-Mn enriched precipitates were Mn6Ni16Si7. Voids were observed in γ austenite. The higher thermal expansion coefficient and faster void swelling rate of γ austenite might be responsible for its susceptible to the formation of voids. Ni-Si enriched clusters were detected at the edges of voids. However, diffraction patterns from the γ austenite, where containing voids, did not reveal the evidence of second phase. Therefore, these Ni-Si enriched clusters might be precursors of Ni-Si precipitates. In addition, irradiated induced Cr depletion, Si and Ni enrichment at γ austenite grain boundaries were detected under STEM/EDS.
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
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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
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
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