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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
Presentation Title Corrosion Behaviour of Laser Powder Bed Fused Inconel 625 in Hydrogenated High Temperature Water
Author(s) Emily Rose Lewis, Alexandra Dickinson-Lomas, Jonathan Duff, Amanda Cruchley, Nick Cruchley, Yu-Lung Chiu, Fabio Scenini, Moataz M. Attallah, Sam Cruchley
On-Site Speaker (Planned) Emily Rose Lewis
Abstract Scope Laser powder bed fusion (PBF-LB) introduces enhanced design flexibility for complex geometry components at high temperatures in water-cooled nuclear reactors. PBF-LB Inconel 625 (IN625) Ni superalloy is a prime candidate due to its excellent corrosion resistance, however microstructural and chemical anisotropy remain following building and post-processing. The effect of as-built microstructure, heat treatment, and surface finishing on the short-term (500, 1500 h) corrosion behaviour of PBF-LB IN625 were investigated in hydrogenated high temperature water. Complementary analytical and advanced materials characterisation techniques, including SEM, TEM, EDS, XRD, and EBSD, were employed to evaluate microstructure, and its role on corrosion. The role of grain texture and surface roughness is discussed in the context of oxidation behaviour. A duplex oxide scale formed, comprised of a Ni(Fe,Cr)2O4 crystallite outer layer upon a continuous Cr-rich inner layer. Scale morphology was altered by surface finish, where differences in grain texture were found to enhance spinel growth.
Proceedings Inclusion? Planned:
Keywords Additive Manufacturing, High-Temperature Materials, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Meshless Peridynamics Framework for Environmentally-induced Corrosion Cracking and Fracture
A Study on Stressed Ferritic/Martensitic Steel Weldments Exposed to High-temperature Liquid Sodium
Characterization of Oxide Structures on Zirconium Alloys
Charged Point Defect Transport through Passivating Oxide Films Simulated with Cluster Dynamics Models
Coatings for LWR Control Rod Assembly for Improved Accident Tolerance and High Burnup Fuel Cycle
Corrosion Behavior of 316L Stainless Steel in Liquid Lead-bismuth Alloys under Proton Radiation
Corrosion Behavior of Pre- and Post-irradiated Metals in Molten Chloride Salts
Corrosion Behaviour of Laser Powder Bed Fused Inconel 625 in Hydrogenated High Temperature Water
Corrosion Mechanism of Cold Worked 316 Stainless Steel in Molten FLiNaK Salt
Dual Irradiation-corrosion of Reduced Activation Ferritic Martensitic Steels for Fusion Applications
E-22: Corrosion Study of a Candidate Material for a Novel Telescopic Control Rod Design for High Temperature Gas Cooled Reactor Height Reduction
E-23: Experimental Design to Study Tribocorrosion Resistance of Perhydropolysilazane-derived Coatings on AISI 304 Steel
E-24: Slow Strain Rate Testing of Two Alumina Forming Austenitic Alloys In Liquid Lead and Lead-bismuth Eutectic
Environmental Induced Defects on the Microstructure of Nuclear Graphite
Evolution of Molten Salt Corrosion Morphology Under the Presence of Irradiation
Extreme Temperature Metallic Sodium Corrosion Resistance of APMT
High Temperature Liquid Lithium Corrosion
Impact of Elastic Stress on the Corrosion Behavior of 316H Stainless Steel By Molten FLiNak
In-situ Corrosion Monitoring of Inconel 625 in the Molten Salt Using Natural Convection Microloop by Radioactive Isotope Tracking
In-situ Irradiation and Molten Fluoride Salt Corrosion of Structural Alloys with 3D EBSD Reconstruction
Investigating the Corrosion Mechanisms of Ni-Cr alloys in Molten Fluoride Salt
Investigation of Oxidation Behavior on Mo-doped FeCrAl Alloys in Low-temperature (400°C) and High-temperature (1200°C) Steam Environments
Mesoscale Modeling of Structural Alloy Corrosion in Molten Salt Reactor
Molten Salt Corrosion of Proton Irradiated Additively Manufactured 316L Stainless Steel Doped with Hafnium
New Insights into the Internal Oxidation Mechanism of 15-15Ti in the Lead-bismuth Eutectic Coolant
Structure-property Relationships in Long-term Thermally Aged HT9
Structure-property Relationships in Long-term Thermally Aged T91 and T92
Studies of Complexation of Ni-Cr in Molten Salts Using Machine Learning Interatomic Potentials
The Effect of Using KOH Instead of LiOH on Corrosion Behavior of Inconel 600 in Simulated PWR Water Chemistry
The Role of Coupled Thermodynamic-kinetic Processes on the Environmental Degradation of Materials in Advanced Nuclear Reactors
Impact of Pre-irradiation and Water Chemistry on In-situ Irradiation-corrosion Behavior of Zircaloy-4

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