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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Effects of Post-Processing Variability on Radiation Response of Additively-Manufactured HT9
Author(s) Pengyuan Xiu, Niyanth Sridharan, Kevin Field
On-Site Speaker (Planned) Pengyuan Xiu
Abstract Scope In this study, the radiation response of an additively manufactured (AM) HT9 alloy using laser powder blown directed energy deposition (DED) was studied. Three HT9 variants were investigated, one directly after DED (as-built, or ASB) and two post-build heat-treated following DED (called ACO3 and FCRD). The unirradiated microstructures varied significantly with the ASB specimen being highly defective (≥1014/m2 estimated) while the ACO3 and FCRD alloys exhibited dislocation densities of 2.261014/m2 and 3.581014/m2 respectively. The variants were dual-ion irradiated to the damage level of 16.6 dpa and 4 He appm/dpa at 445C to study the radiation response. Radiation induced cavity densities were 3.11022/m2, 7.01021/m2, and 4.91021/m2, with the size of 4.31.7nm, 6.46.7nm, and 4.32.5nm for ASB, ACO3 and FCRD respectively. Nanometric Ni/Si-rich clusters existed only in the ACO3 and FCRD variants with densities around 81021/m2 after irradiation. The implications of the AM-based sink strengths on the radiation tolerance will be discussed.
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 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
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