| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components IV
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| Presentation Title |
Mechanical response of ion irradiated HT9 with in-situ straining and cantilever bending tests |
| Author(s) |
Pengcheng Zhu, Dongyue Xie, Hyosim Kim, Nan Li, Yongqiang Wang |
| On-Site Speaker (Planned) |
Pengcheng Zhu |
| Abstract Scope |
9-12% Cr ferritic-martensitic steel are promising candidates for the structural components in Generation IV fission reactors. Ion irradiation is an important method to accelerate the study on irradiation effects and optimization of alloy elements. The minimal tensile bars of alloys HT9 with different nitrogen content were subject to 3.5 MeV Fe2+ ion irradiation at 450 °C to 200 dpa under constant load, to investigate the creep properties under extreme conditions combining irradiation and in-situ straining. The cantilever beams were prepared on the HT9 samples irradiated with 9 MeV Fe3+ ions at 450 °C to 20 dpa. The in-situ bending tests will be conducted under SEM at various temperatures to evaluate the Ductile-brittle transition temperature (DBTT). The TEM characterizations on the deformed samples will elucidate the fundamental understanding of the mechanical degrading mechanisms. This multi-scale study can also provide insight in effect of nitrogen on mechanical properties. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Iron and Steel, Mechanical Properties, Characterization |