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About this Symposium

Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Sponsorship TMS Structural Materials Division
TMS: Corrosion and Environmental Effects Committee
Organizer(s) Trishelle Copeland-Johnson, Idaho National Laboratory
Suraj Y. Persaud, Queen's University
Osman Anderoglu, University of New Mexico
Adrien Couet, University of Wisconsin-Madison
Scope Abstract: Advanced nuclear reactors are a promising addition to expanding the domestic and worldwide sustainable energy portfolio in the wake of climate change. However, the qualification of materials suitable to meet the operational needs of different reactor technologies has not matured, especially concerning corrosion performance in molten salt and liquid metal fission designs and fusion designs. The aim of this symposium is to provide a space to discuss current progress in elucidating the interfacial corrosion mechanisms of structural materials subjected to these extreme operating environments.

This symposium will prioritize discussions on:
• Corrosion mechanisms between structural materials and liquid tritium breeders (e.g. PbLi, Li, FLiBe, etc.).
• Corrosion mechanisms between structural materials and liquid metals (e.g. lead, sodium, etc.)
• Synergistic effects of operation conditions (e.g. irradiation, fission products, tritium, etc.) on the corrosion mechanisms between structural materials in molten salt and liquid metal systems.

Abstracts Due 07/29/2025
Proceedings Plan Planned:

PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE


Advanced High Strength steel initial evaluation characterization for nuclear application
An integrated modeling and experimental framework for investigating the synergy between irradiation and molten salt corrosion in conventional and additively manufactured 316H alloys
Best Practices for Measurement of Impurities in FLiNaK and FLiBe
Chloride Fuel Salt at Equilibrium: Corrosion
Comparative Study on Stress Assisted Corrosion Behavior of Stainless Alloy 718 & High Entropy Alloy Al0.1CrCoFeNi in a Molten NaCl-Na2SO4 Salt
Critical Assessment of Corrosion Resistance and Mechanical Integrity of traditional and advanced steels in liquid sodium.
Density Functional Theory Study of Charge Distribution at Metal-ZrO2 Interface
Development of a Magnetohydrodynamic PbLi Loop for Corrosion Testing of Candidate Blanket Materials
Effects of Oxygen Contaminated Liquid Sodium on the Degradation of Austenitic and Ferritic/Martensitic Stainless Steels
Investigating the Impact of Lead-Lithium Eutectic on Structural Materials for Fusion Breeding Blankets
Liquid metal penetration or rapid oxide growth -- Investigating heavy liquid metal inclusions in porous Fe-oxides
Novel Coatings for Enhanced Performance and Corrosion Resistance of LFR
Oxidation behavior of Zr-Nb Alloys in Air and Steam-Containing Environments
Predicting Co-segregation Tendency of Cesium and Tellurium via Ab Initio and Machine Learning Methods
Simultaneous proton irradiation induced delocalization of liquid metal penetration in Fe-based alloys exposed to liquid Lead at 675°C
Static corrosion of SS316H in Purified NaF-KF-UF4-UF3
Thermomechanical, lead corrosion and thermal stability assessment of innovative Alumina Forming Austenitic Alloys for LFRs
Validation of Inert Gas Fusion for Oxygen Analysis in Fluoride Salts: A Cross-Sector Approach for Nuclear-Grade Assurance


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