| About this Abstract |
| Meeting |
MS&T21: Materials Science & Technology
|
| Symposium
|
Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
|
| Presentation Title |
Effect of Ion Irradiation on the Corrosion of 304SS in PWR Simulated Water Chemistry |
| Author(s) |
Fu-Yun Tsai, Ryan Schoell, Khalid Hattar, Djamel Kaoumi |
| On-Site Speaker (Planned) |
Fu-Yun Tsai |
| Abstract Scope |
A study on the effects of ion irradiated microstructure on corrosion of 304SS in simulated Pressurized Water nuclear Reactor conditions was conducted. Coupons of 304SS were irradiated with 10 MeV Au ions to 10 displacements per atom on average over 1 μm thickness below surface. Corrosion was conducted in a recirculating autoclave in simulated PWR primary water condition (325 ℃, 2200 psi, 30 cc H2/kg of H2O at STP) for a total of 6 weeks and samples were investigated at intervals of about 7 days. Transmission Electron Microscopy (TEM) of cross-sectional samples was used to study the oxide formation through diffraction analysis and kinetics through oxide-thickness measurements in both irradiated and non-irradiated regions. Results showed differences in oxide depth and shape between irradiated and non-irradiated regions although the oxide phases were similar. A discussion was conducted to substantiate the effects of irradiation. |