| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
Molten Salt Corrosion of Proton Irradiated Additively Manufactured 316L Stainless Steel Doped with Hafnium |
| Author(s) |
Laura Hawkins, Jingfan Yang, Zhihan Hu, Michael Woods, Ruchi Gakhar, Lin Shao, Xiaoyuan Lou, Daniel Murray, Lingfeng He |
| On-Site Speaker (Planned) |
Laura Hawkins |
| Abstract Scope |
In next-generation molten-salt reactors, understanding the microstructural evolution in extreme environments requires rigorous experimentation on structural materials. This study combines molten salt corrosion, proton irradiation, and high-throughput materials characterization to investigate the impact of irradiation damage on the corrosion behavior of additively manufactured 316L stainless steel doped with hafnium. Previous research has indicated that hafnium effectively mitigates both irradiation damage and chromium depletion during molten salt corrosion. This work presents new findings by examining samples subjected to 2 MeV proton irradiation to 1 dpa, followed by molten salt corrosion in eutectic NaCl-MgCl2 at 700 °C for 30 and 240 hours. Advanced characterization techniques, including scanning electron microscopy, transmission electron spectroscopy, and energy dispersive X-ray spectroscopy, will be used to analyze the morphology and microstructure of the Hf gradient regions, comparing the results to non-irradiated samples. These insights contribute to developing more resilient structural materials for next-generation molten-salt reactors. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Additive Manufacturing, Environmental Effects, Nuclear Materials |