About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
|
Symposium
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Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
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Presentation Title |
The Effect of Using KOH Instead of LiOH on Corrosion Behavior of Inconel 600 in Simulated PWR Water Chemistry |
Author(s) |
Fu-Yun Tsai, Chuanzhen Zhou, Minsung Hong, Kayla Yano, Daniel Schreiber, Mukesh Bachhav, Peter Hosemann, Djamel Kaoumi |
On-Site Speaker (Planned) |
Fu-Yun Tsai |
Abstract Scope |
A study on the effects of KOH or LiOH on corrosion of Inconel 600 in simulated Pressurized Water nuclear Reactor conditions was conducted. Coupons of I600 were corroded in different autoclaves which includes LiOH or KOH with different chemistries up to crevice water chemistry in simulated PWR primary water condition (325 ℃, 2200 psi, (initial) 30 cc H2/kg of H2O at STP) for 7 days and 30 days. Transmission Electron Microscopy (TEM) of cross-sectional samples was used to characterize the formed oxide through diffraction analysis, as well as Secondary Ion Mass Spectrometry and Atom Probe Tomography and Electrochemical Impedance Spectroscopy. A discussion comparing the results in the two environments was conducted to substantiate the effects of replacing LiOH with KOH and it was found that KOH not only does not worsen the corrosion behavior of I600 at normal operating concentrations but may in fact be beneficial in crevice-like conditions. |
Proceedings Inclusion? |
Planned: |
Keywords |
Other, Characterization, |