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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
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Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Alumina Scale Stability Under Combined High Temperature Liquid Metal Corrosion and Neutron Irradiation
Corrosion of Advanced Materials Exposed to High Temperature Helium
Development and Construction of a Liquid Lead-Lithium Loop at UNM
Effects of Sodium Exposure on Tensile Properties of Advanced Reactor Materials
Evaluating Compatibility of Structural Materials for a FLiBe Fusion Breeder Blanket
Evaluation of Compatibility of Steel, Vanadium Materials and Steel-Insulator-Steel Structures With High Temperature Liquid Lithium
Impact of Oxidation and Helium Irradiation-Induced Defects in Fe-18Cr Samples
In-Situ Characterization of Heavy Liquid Metal Eutectic During Corrosion Using Laser Ablation Inductively Coupled Plasma Mass Spectrometry (LA-ICPMS)
Influence of Proton Irradiation on Corrosion in Liquid Lead
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Thermomechanical, Lead Corrosion and Thermal Stability Assessment of Innovative Alumina Forming Austenitic Alloys for LFRs

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