| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Mechanical Response of HT9 and T91 under Dual-ion and Neutron Irradiations |
| Author(s) |
Pengcheng Zhu, Shradha Agarwal, Steven Zinkle |
| On-Site Speaker (Planned) |
Pengcheng Zhu |
| Abstract Scope |
9-12% Cr ferritic/martensitic steels are promising candidate structural materials for Generation IV fission reactors. HT9 and T91 alloys were subjected to dual-ion (9 MeV Fe<sup>3+</sup> and 3.42 MeV He<sup>2+</sup>, 445 and 520 ℃) and BOR60 reactor irradiations to quantify the possibility of using ion irradiation to simulate neutron irradiation in microstructures and mechanical properties. Nanoindentation hardness testing was performed with Berkovich indenter to obtain information on 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 mechanical properties form nanoindentation data will be used based on our previous study on FeCr binary alloys. The results of TEM characterization of the bubbles and dislocation loops will be summarized, and detailed comparisons will be provided on the predicted (dispersed barrier hardening superposition) vs. measured strength values of the irradiated specimens. |
| Proceedings Inclusion? |
Undecided |