| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
Development of Microscale In-situ Corrosion and Irradiation Experiment |
| Author(s) |
Hyosim Kim, Franziska Schmidt, Matthew Chancey, Yongqiang Wang, Blas Pedro Uberuaga |
| On-Site Speaker (Planned) |
Hyosim Kim |
| Abstract Scope |
Structural materials in advanced sodium-cooled reactors are expected to withstand extreme environments including high temperature, corrosive media, high-dose radiation, and stress. It is challenging to test and screen candidate materials under reactor-like conditions where these extreme conditions concurrently degrade the materials. In this study, an in-situ corrosion and irradiation experiment was conducted on the microscale for the first time using focused ion beam (FIB) preparation and ion irradiation. A small volume of molten salt was loaded in the pit of Ni matrix and thin cover (~1 μm thick) from the same material was made and welded on the surface using a FIB. This salt loaded chamber was irradiated using 5 MeV Ni ions at 800 °C to 50 dpa to ensure full ion penetration through the cover. The interface of the cover and the salt was examined using SEM and TEM to observe the effect of concurrent corrosion and irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Copper / Nickel / Cobalt |