| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
Characterisation of Oxide Dispersion Strengthened Steels for Nuclear Fusion Application |
| Author(s) |
Viacheslav Kuksenko |
| On-Site Speaker (Planned) |
Viacheslav Kuksenko |
| Abstract Scope |
Ferritic Oxide Dispersion Strengthened (ODS) steels are promising candidates for high temperature applications in future fusion energy reactors. United Kingdom Atomic Energy Authority recently produced twelve Fe-14Cr-3W-0.4Ti-Y ODS grades with variable yttrium oxide content (0.2 to 0.4%) and hot-isostatic pressing parameters (T=1100 to 1160°C, Pressure=110 to 200MPa). This paper presents a quantitative description of mechanical properties of the obtained material linked to the observed differences in microstructure. Selected samples have been irradiated at 350°C up to doses of 1, 10 and 100 dpa. Nanoindentation did not demonstrate noticeable hardening up to 10 dpa with hardening of 10 to 15% between 10 and 100dpa. These results will be discussed and linked to atom probe tomography data on stability of Fe-Cr based matrix and yttria based precipitates. These results are important for the understanding of the basic mechanisms of stability and decomposition of this material under irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Iron and Steel, Characterization, High-Temperature Materials |