About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
| Presentation Title |
Examining Microstructures and Mechanical Properties of Neutron and Ion Irradiated T91, HT9 and 800H Alloys |
| Author(s) |
Pengcheng Zhu, Shradha Agarwal, Steven Zinkle |
| On-Site Speaker (Planned) |
Pengcheng Zhu |
| Abstract Scope |
9-12% Cr ferritic-martensitic steel (T91, HT9) and austenitic alloy 800H are promising candidates for the structural components in Generation IV fission reactors. Alloys T91, HT9 and 800H were irradiated with neutrons (BOR60 reactor) and dual-ions (9MeV Fe3+ and 3.24MeV He2+) from 376 to 520 ℃ with damage from 16.6 to 72 dpa, to quantify the possibility of using ion irradiation to simulate neutron irradiation in microstructures and mechanical properties. Nanoindentation testing was performed to obtain the bulk hardness of the dual-ion irradiated samples due to limited damage volumes. For the neutron irradiated samples, both nanoindentation and Vickers hardness testing were conducted. An accurate way to extract bulk hardness from nanoindentation data will be used based on our previous study on FeCr alloys. The results of TEM characterization of the bubbles and dislocation loops will be provided to compare the predicted (dispersed barrier hardening) and measured strength of the irradiated specimens. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Iron and Steel, Nuclear Materials, Characterization |