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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Development of a Magnetohydrodynamic PbLi Loop for Corrosion Testing of Candidate Blanket Materials
Author(s) Xavier Angus, Daniel Levario, Marie Romedenne, Claude De lamater-Brotherton, Sergey Smolentsev, G. Ivan Maldonado, Nicholas Brown, Son Quang, Jennifer Espersen, Osman Anderoglu
On-Site Speaker (Planned) Xavier Angus
Abstract Scope Advancing the understanding of eutectic lead-lithium (PbLi) corrosion behavior in flowing magnetohydrodynamic (MHD) environments remains essential for the deployment of liquid metal breeder blankets in fusion systems. Building on previous work outlining the design of a high temperature forced convection PbLi loop at the University of New Mexico, this study presents the commissioning and initial operation of the experimental system. The constructed loop, fabricated from SS316 and equipped with a high-field (~2 T) electromagnet, now includes operational instrumentation such as a differential pressure sensor for magnetohydrodynamic (MHD) flow diagnostics. ICP-OES analysis has been used to assess the chemical composition of the eutectic PbLi, and preparations are underway for corrosion testing at temperatures up to 550 °C. The system features interchangeable test sections to accommodate tubing of various materials and surface coatings to evaluate corrosion performance under high-temperature MHD conditions.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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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