| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
Corrosion Behavior of 316L Stainless Steel in Liquid Lead-bismuth Alloys under Proton Radiation |
| Author(s) |
Wande Cairang, Weiyue Zhou, Paola Amadeo , Kevin Woller, Michael Short |
| On-Site Speaker (Planned) |
Wande Cairang |
| Abstract Scope |
Understanding the coupling between radiation and corrosion in nuclear materials is crucial for nuclear energy technologies, as material will be exposed to both simultaneously while in service. This research examines the impact of simultaneous proton radiation on the corrosion of 316L stainless steel exposed to liquid lead-bismuth alloys. We investigate the influence of temperature and bismuth concentration on corrosion behavior and morphology at temperatures of 600°C and 675°C, along with bismuth concentrations of 5%, 10%, and 20%. These conditions were chosen to vary (1) differences in diffusivities in grains vs. at grain boundaries, and (2) solubilities of metallic elements in the mixture affecting interfacial selective dissolution. Cross-sectional SEM observation and statistical analysis using ImageJ software are used to determine corrosion depth and illustrate differences in corrosion morphology. Additionally, we seek to unravel the fundamental mechanisms underlying the observed phenomena, as predicting corrosion rates and modes allows prediction of in-reactor performance. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Environmental Effects |