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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
Presentation Title Corrosion Studies of SS 316H, Haynes 230 and Haynes 282 in GaInSn Eutectic
Author(s) Qiufeng Yang, Priyanshi Agrawal, Ruchi Gakhar, Michael Heighes, Peng Xu, Ben Baker, Justin Johnson, John Jackson, Doug Crawford
On-Site Speaker (Planned) Qiufeng Yang
Abstract Scope GaInSn eutectic (e-GaInSn) has been proposed to be excellent coolant in advanced nuclear reactor due to its low melting point, high thermal conductivity, large heat capacity and low vapor pressure. The structural material corrosion resulting from the coolant is inevitable and has been a major concern for the application of e-GaInSn. Alloys including SS 316H, Haynes 230 and Haynes 282 have good mechanical properties and corrosion resistance at elevated temperatures, rendering them promising candidates as structural materials in reactors. However, thorough corrosion studies in e-GaInSn are scarce. More comprehensive studies are needed to fully understand their corrosion behavior. In the present study, corrosion studies of SS 316H, Haynes 230 and Haynes 282 in e-GaInSn at 500 °C for test durations varying up to 1700 hours will be discussed. A comparative study on corrosion mechanisms of these three structural materials using combinatorial mechanical and surface analysis will be presented.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Alumina Scale Stability Under Combined High Temperature Liquid Metal Corrosion and Neutron Irradiation
Corrosion of Advanced Materials Exposed to High Temperature Helium
Corrosion Studies of SS 316H, Haynes 230 and Haynes 282 in GaInSn Eutectic
Development and Construction of a Liquid Lead-Lithium Loop at UNM
Effects of Sodium Exposure on Tensile Properties of Advanced Reactor Materials
Evaluating Compatibility of Structural Materials for a FLiBe Fusion Breeder Blanket
Evaluation of Compatibility of Steel, Vanadium Materials and Steel-Insulator-Steel Structures With High Temperature Liquid Lithium
Impact of Oxidation and Helium Irradiation-Induced Defects in Fe-18Cr Samples
In-Situ Characterization of Heavy Liquid Metal Eutectic During Corrosion Using Laser Ablation Inductively Coupled Plasma Mass Spectrometry (LA-ICPMS)
Influence of Proton Irradiation on Corrosion in Liquid Lead
Liquid Lithium Corrosion of Structural Fusion Materials
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Thermomechanical, Lead Corrosion and Thermal Stability Assessment of Innovative Alumina Forming Austenitic Alloys for LFRs

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