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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Best Practices for Measurement of Impurities in FLiNaK and FLiBe
Author(s) Nayoung Kim, Weiyue Zhou, Kevin Woller, Michael Short, Alexander A. Khechfe, Guiqiu Zheng, Caroline Sorensen
On-Site Speaker (Planned) Nayoung Kim
Abstract Scope Fluoride molten salts, especially FLiNaK and FLiBe, are promising fuel and coolant materials in the nuclear industry for their favorable thermophysical and neutronic properties. However, metallic and oxygen impurities present in these salts can induce corrosion of structural materials. Although ICP-MS and combustion analysis are commonly employed to quantify these impurities, openly published, standardized procedures do not yet exist, hindering direct comparison of different data. This study investigates how variations in sample preparation – specifically sampling method, particle size, acid mixture, and digestion technique – affect impurity measurements in FLiNaK and FLiBe. Key impurity elements (Fe, Cr, Ni) were measured, and known quantities of dopants were used to validate the accuracy of the procedure. Additionally, modifications were made to ensure the safe handling of FLiBe. The methodology suggested provides a foundation for standardizing impurity analysis in molten salts, enabling more consistent and reliable impurity-driven corrosion research in salt systems.
Proceedings Inclusion? Planned:
Keywords Characterization, High-Temperature Materials, 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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