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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Thermomechanical, lead corrosion and thermal stability assessment of innovative Alumina Forming Austenitic Alloys for LFRs
Author(s) Mauro Brignone, Daniele De Caro, Marco Poletti
On-Site Speaker (Planned) Mauro Brignone
Abstract Scope The development of new generation Lead-cooled Fast Reactors (LFRs) encounters the key challenge of long-term degradation of structural materials when exposed to liquid lead. Current research identifies alumina-forming austenitic (AFA) steels as a promising material class for structural applications in LFRs. A novel AFA steel composition has been developed and optimized to match challenging requirements of nuclear-grade materials. The experimental activity was carried out by casting 80 kg ingot through VIM and VAR processes. Thermomechanical tests were conducted using a Gleeble machine to identify optimum forming parameters afterwards used for the hot rolling of larger sheets. The material corrosion resistance was assessed through Pb corrosion tests for 1000 hours at 600°C. Additionally, mechanical tests both in air and in lead were executed to evaluate the corrosion and stress combination effect. Comprehensive bulk characterization techniques, including SEM, XRD, and OM, have been utilized to analyze microstructure, phase transformations and rupture mechanisms.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Mechanical Properties

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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