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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
Presentation Title The Role of Coupled Thermodynamic-kinetic Processes on the Environmental Degradation of Materials in Advanced Nuclear Reactors
Author(s) Marie Romedenne, Rishi Pillai, Dino Sulejmanovic, Ian Greenquist, Bruce Pint
On-Site Speaker (Planned) Marie Romedenne
Abstract Scope Advanced nuclear reactor technologies, with the use of liquid metals or molten salts, have the potential to improve safety, efficiency and cost competitiveness of nuclear energy. However, significant challenges exist in the design, selection and qualification of structural materials due to the limited knowledge on the key parameters governing corrosion induced degradation mechanisms and thereby material lifetimes. In the present work, the role of alloy thermodynamics and kinetics in material degradation during exposures in high temperature corrosive environments will be discussed combining experimental and computational methods. The fundamental role of coupled thermodynamic-kinetic processes on the environmental degradation of various material/coolant systems: Ni-based alloy/molten salt; Fe-based alloy/liquid sodium and Zr-based alloy/ liquid PbBiSn will be presented.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Computational Materials Science & Engineering

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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