| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
In-situ Irradiation and Molten Fluoride Salt Corrosion of Structural Alloys with 3D EBSD Reconstruction |
| Author(s) |
Cole Evered, Michael Tonks, Kumar Sridharan, Adrien Couet |
| On-Site Speaker (Planned) |
Cole Evered |
| Abstract Scope |
With the current development of molten salt-cooled advanced nuclear reactors comes the limited selection of code qualified structural materials available to build these reactors. Even among these already qualified materials, understanding of how they perform under simultaneous irradiation and corrosion is also limited. In-situ irradiation and corrosion of SS316 with 2.8 MeV protons at 500°C up to 0.015 dpa at a damage rate of 1.4x106 dpa/s resulted in limited corrosion of the non-irradiated area and a severe increase in corrosion throughout the irradiated area. The grain boundaries show particular susceptibility to corrosion under irradiation resulting in molten salt penetration into the alloy. SEM/EDS analysis shows a redistribution of alloying elements at the irradiated surface grain boundaries with more limited segregation in the bulk. EBSD coupled to 3D reconstruction is underway to correlate grain boundary attack to local grain orientation. New irradiation results to higher total damage will also be presented. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Other, Other, |