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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Predicting Co-segregation Tendency of Cesium and Tellurium via Ab Initio and Machine Learning Methods
Author(s) Ho Lee, Kwanghee Lee, Sangtae Kim
On-Site Speaker (Planned) Ho Lee
Abstract Scope Grain boundary segregation of fission products influences the integrity of austenitic stainless steels in molten salt reactor environments. Especially, the co-presence of cesium and tellurium, two major fission products of MSRs, embrittles AISI 316, whereas Cs alone does not. Here, we employ density functional theory calculations to compute the co-segregation energies of Cs-Te in four γ-Fe symmetric tilt GBs, along with individual segregation energies of Cs and Te. From each Cs and Te segregated structures, we extracted physical descriptors, including local atomic-environment metrics, elastic contributions and electronic features. These descriptors were employed to train a gradient-boosting machine-learning model to predict co-segregation energies in unseen γ-Fe GBs. The trained model reveals that changes in local atomic-environment induced by Cs segregation influences co-segregation behavior of Cs-Te mixtures. These findings provide a computationally efficient framework for designing Fe-based alloys that mitigate loss of ductility due to interactions between fission products and structural alloys.
Proceedings Inclusion? Planned:
Keywords Computational Materials Science & Engineering, Machine Learning, Iron and Steel

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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