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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Novel Coatings for Enhanced Performance and Corrosion Resistance of LFR
Author(s) Andrea Ventrella, Davide Loiacono, Francisco Garcia Ferrč
On-Site Speaker (Planned) Andrea Ventrella
Abstract Scope Newcleo is developing Lead-cooled fast reactor (LFR) Small Modular Reactors (SMRs) for next-generation nuclear energy. LFRs face challenges with materials that withstand high temperatures and corrosive liquid lead. This study explores novel coating techniques—such as PVD, CVD, thermal spray, laser cladding, and weld overlay with AFA steel—to enhance material performance and corrosion resistance. Coated materials were tested under simulated LFR conditions (up to 600°C), evaluating their ability to prevent lead penetration and maintain integrity. Preliminary tests in dynamic molten lead environments and ionic irradiation show promising results. The presentation highlights the performance of various coatings, including FeCrAl, ceramic nitrides, TiN, and alumina-based materials. These coatings, applied in different thicknesses, demonstrate potential for improving the durability of LFR components in extreme environments, supporting the development of safer, more efficient nuclear reactors.
Proceedings Inclusion? Planned:
Keywords Surface Modification and Coatings, Characterization, 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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