About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
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Symposium
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Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
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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, |