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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Oxidation behavior of Zr-Nb Alloys in Air and Steam-Containing Environments
Author(s) Sean Li, Chaitanya S. Deo, Remi Dingreville, Scott Monismith, Nate Bianco, Preet M. Singh
On-Site Speaker (Planned) Sean Li
Abstract Scope Zr-based alloys are essential in nuclear reactors due to their superior irradiation stability and mechanical properties. Recently developed Zr-based alloys often incorporate Nb as a key alloying element to enhance performance. This study systematically investigates the effect of Nb addition on the oxidation behavior of binary Zr-Nb alloys with hypoeutectoid, eutectoid, and hypereutectoid compositions. Alloys produced using an electric arc furnace were tested for their oxidation behavior in both air and steam environments at temperatures ranging from 200 °C to 500 °C. Oxide scale morphology and structure were characterized using XRD, SEM, and EDS. Oxidation rates were generally lower in steam containing environments than in air under otherwise equivalent test conditions. Comparisons between oxides formed in air and steam revealed significant differences in composition and morphology, emphasizing the importance of environment on high-temperature oxidation behavior. These findings provide critical insights for the design and selection of Zr-based alloys for high temperature applications.
Proceedings Inclusion? Planned:
Keywords High-Temperature Materials, Nuclear Materials, Environmental Effects

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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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