| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Metals and Ceramics
|
| Presentation Title |
H-54: Mechanical Response of FeCr Alloys under Thermal Aging and Irradiation |
| Author(s) |
Pengcheng Zhu, Yajie Zhao, Shradha Agarwal, Steven Zinkle |
| On-Site Speaker (Planned) |
Pengcheng Zhu |
| Abstract Scope |
High chromium ferritic/martensitic steels are promising candidate structural materials for Generation IV fission and fusion reactors. Fe18%Cr and Fe25%Cr were subjected to thermal aging (100-900 hours at 475 °C) to produce Cr-rich α’ precipitates of varying size and density. Nanoindentation hardness testing was performed with Berkovich and spherical indenters to obtain information on yield and ultimate strength. The Berkovich indentations provide information on the bulk hardness of nanoscale irradiated volumes, while spherical indentations provide work hardening capacity information. The aged materials were subsequently irradiated with 8 MeV Fe<sup>+</sup> ions (0.35 dpa at 475 °C, dose rates of ~10<sup>-5</sup> and 10<sup>-4</sup> dpa/s), and the nanoindentation response was compared with the thermal aged specimens. The results of TEM and APT characterization of the α’ precipitates will be summarized, and detailed comparisons will be provided on the predicted (dispersed barrier hardening superposition) vs. measured strength values of the aged and irradiated specimens. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |