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Meeting 2024 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
Sponsorship TMS Structural Materials Division
TMS: Corrosion and Environmental Effects Committee
Organizer(s) Trishelle Copeland-Johnson, Idaho National Laboratory
Cheng Sun, Clemson University
Caitlin Huotilainen, TerraPower
Nidia C. Gallego, Oak Ridge National Laboratory
Suraj Y. Persaud, Queen's University
Osman Anderoglu, University of New Mexico
Adrien Couet, University of Wisconsin-Madison
Julie D. Tucker, Oregon State University
Scope Advanced nuclear reactors are a promising addition to expand the domestic and worldwide sustainable energy portfolio in the wake of climate change. However, qualification of materials suitable to meet the operational needs of different reactor technologies has not matured, especially for corrosion performance. According to the World Corrosion Organization, the annual direct cost of corrosion is over 1.8 trillion dollars worldwide. This issue extends into maximizing the operational lifespan of advanced nuclear reactors including molten salt nuclear reactors, sodium-cooled and lead-cooled fast reactors, and high temperature gas-cooled reactors, which introduce operational environments that require the highest performing nuclear materials to construct. Thus, there is an increasing need to expand the fundamental framework of the corrosion behaviors of nuclear structural materials. The aim of this symposium is to provide a space to discuss current progress in our understanding of how the corrosion mechanism of nuclear structural materials is impacted by the environmental stressors introduced by advanced nuclear reactors, including temperature, corrosion medium, atmospheric composition, the presence of actinide and transuranic species, ion/neutron irradiation, etc.

Topic areas for this symposium include but are not limited to:

• The impact of actinide and fissile by-product species on corrosion mechanisms.
• The impact of irradiation on the corrosion behaviors of materials.
• The relationship between environmentally induced (e.g. temperature, irradiation, etc.) phase transformations and corrosion mechanisms.
• The intersectionality between radioactive species and irradiation on the corrosion mechanism in molten salt environments
• High temperature corrosion of nuclear structural materials and cladding in liquid sodium, lead, or lead-bismuth eutectic coolant mixtures
• Structural alloy and graphite corrosion at high temperature conditions
• The intersectionality between mechanically induced phenomena (e.g. environmentally-induced stress corrosion cracking) and corrosion mechanism

Abstracts Due 07/15/2023
Proceedings Plan Planned:

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 (400C) and High-temperature (1200C) 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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