Conference Logo ProgramMaster Logo
Conference Tools for 2026 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools

About this Abstract

Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
Presentation Title Chloride Fuel Salt at Equilibrium: Corrosion
Author(s) Randall Chiu, Nathanael Gardner, Michael Borello, Raluca Scarlat, Peter Hosemann
On-Site Speaker (Planned) Randall Chiu
Abstract Scope Actinide-bearing chloride and fluoride salts, such as NaCl-UCl3 eutectic, are used fuel in advanced molten salt reactor designs. The composition of the fuel salt changes over the lifetime of the reactor due to burnup, fission product buildup, refueling, and corrosion. Elsewhere, the effects of the introduction of fission products to NaCl-UCl3 fuel salt on its thermophysical properties are described. In this companion study, those same salt samples are studied for their corrosive effects on metals and alloys that may serve as structural materials. Three NaCl-UCl3 salt reactor states are measured; the initial eutectic feed salt, the equilibrium Na:U ratio composition salt, and the equilibrium Na:U ratio composition with the addition of modeling predicted fission products. The implications for redox control by uranium are discussed.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Iron and Steel, High-Temperature 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

Questions about ProgramMaster? Contact programming@programmaster.org | TMS Privacy Policy | Accessibility Statement