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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Validation of Inert Gas Fusion for Oxygen Analysis in Fluoride Salts: A Cross-Sector Approach for Nuclear-Grade Assurance
Author(s) Christian Zuehlke, Michael Stoddard, Kayden Alderson, Jaron Wallace, Eric Slater, Joshua Tewell
On-Site Speaker (Planned) Christian Zuehlke
Abstract Scope Oxygen content in fluoride salts is critical for controlling redox chemistry, corrosion, and fission product behavior in molten salt reactors (MSRs). Inert Gas Fusion (IGF) offers a direct method for oxygen analysis but faces skepticism when applied to fluoride salts. High temperatures are needed to thermodynamically drive oxygen reactions with carbon, which can exceed the boiling point of lithium, causing volatilization and secondary reactions—such as fluorides attacking the metal or glass components that cause spurious oxygen signals or contaminations. These effects raise concerns about accuracy, precision, and signal linearity. This work brings together Natura Resources, defining nuclear-grade requirements; Bruker AXS, optimizing IGF instrument design; and USREL, developing and validating the method with oxygen-doped standards and spike recovery. Together, we demonstrate that with tailored thermal profiles, fluxes, and calibration protocols, IGF can provide accurate, reproducible oxygen analysis in salts like FLiBe and FLiNaK, supporting broader deployment in nuclear material qualifications.
Proceedings Inclusion? Planned:

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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