About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
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| Presentation Title |
Investigation of Neutron Irradiation Effects on T91 Ferritic/Martensitic Steel for Fusion Reactor Applications |
| Author(s) |
Mahmud Hasan Ovi, Hoon Lee, Tamim Hossain, Intisher Al-Tahmid Omi, James F. Stubbins |
| On-Site Speaker (Planned) |
Mahmud Hasan Ovi |
| Abstract Scope |
Ferritic/martensitic steels, particularly T91, are prime candidates for structural components in fusion reactors due to their favorable mechanical properties and resistance to radiation-induced swelling. This study examines the tensile properties and microstructural evolution of T91 steel subjected to neutron irradiation in the Advanced Test Reactor(ATR) at doses ranging from 0.01 to 10 displacements per atom(dpa) and temperatures of 300°C, 450°C, and 550°C. Room-temperature tensile tests were conducted to assess changes in mechanical behavior, complemented by nanoindentation to evaluate hardness variations. Advanced microscopy techniques, including scanning electron microscopy (SEM), and transmission electron microscopy (TEM), were employed to characterize irradiation-induced defects such as Cr-rich α'-phase precipitates, G-phase formation, and dislocation loop development. Additionally, Fe-9Cr-0.1C and Fe-12Cr-0.2C model alloys, analogous in composition to T91 and HT9 respectively, were investigated to isolate the roles of chromium and carbon in irradiation responses. The findings provide insights into the degradation mechanisms of T91 under neutron irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Mechanical Properties, Iron and Steel |