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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
Presentation Title New Insights into the Internal Oxidation Mechanism of 15-15Ti in the Lead-bismuth Eutectic Coolant
Author(s) Min Wang, Cheng-xu Lu, Ying-che Ma
On-Site Speaker (Planned) Min Wang
Abstract Scope Though providing corrosion protection, internal oxidation generally induces a metal recession. The lead-bismuth eutectic corrosion mechanism, especially the advancing behavior of the oxide/metal (O/M) interface, was investigated at 550 and 600℃ for a candidate LFR cladding material, the austenitic stainless steel 15-15Ti. Island-like Ni-rich areas are often found in the spinel layer and are commonly considered oxidation residues by researchers. However, through special sample preparation, we discovered that these Ni-rich areas in fact originate from the unoxidized metal near the O/M interface. FIB-STEM characterizations show that Ni-rich areas act as Cr-suppliers and Ni-receivers during oxidation, facilitating the O-consumption by Cr-oxidation. Moreover, Ni-rich areas preferentially nucleate on the grain boundary coherently and then grow forward inducing grain boundary migration, obstructing oxygen diffusion by serrating its pathway. The effects of Si addition and Al addition on the anti-corrosion performance promotion, oxide structure, and corrosion mechanisms of 15-15Ti are also studied.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Phase Transformations

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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