| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
Dual Irradiation-corrosion of Reduced Activation Ferritic Martensitic Steels for Fusion Applications |
| Author(s) |
Liam James Hughes, Yu-Lung Chiu, Martin Freer, Joven Lim |
| On-Site Speaker (Planned) |
Liam James Hughes |
| Abstract Scope |
Reduced activation ferritic/martensitic (RAFM) steels have emerged as the favoured choice for the breeder blanket in Tokamak-type fusion reactor designs. Despite their growing prominence, the effects of radiation on corrosion in RAFM steels have not been extensively investigated. In this study, we plan to utilize the dual irradiation-corrosion facility at Birmingham to comprehensively examine this issue. Our primary focus will be on analysing tensile specimens under controlled stress and temperature (523 – 623 K), with and without irradiation. This will enable us to assess the synergistic effects of radiation in a corrosive environment. To gain a deeper understanding of the chemical changes that potentially undermine material performance, we will employ advanced characterization techniques, such as, scanning transmission electron microscopy (STEM). By improving our understanding of the corrosion behaviour of RAFM steels under irradiation, we aim to enhance the overall performance and reliability of breeder blankets in Tokamak-type fusion reactor designs. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |