| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Evaluating mechanical properties of irradiated Ferritic/Martensitic steels with nanoindentation and strengthening model predictions |
| Author(s) |
Pengcheng Zhu, Yajie Zhao, Yan-Ru Lin, Valentin Pauly, Stephen Taller, Jean Henry, Shradha Agarwal, Steven Zinkle |
| On-Site Speaker (Planned) |
Steven Zinkle |
| Abstract Scope |
Ion irradiation is an important and efficient method to emulate the damages caused by neutron irradiation. Nanoindentation and strengthening model predictions are widely used to evaluate the bulk mechanical properties after ion irradiation. Nanoindentation results are frequently susceptible to considerable uncertainties due to indentation size effects, pileup effects, and potential influence of surface quality. Therefore, a scientific nanoindentation test protocol is imperative to acquire accurate bulk equivalent hardness data. Microstructure-based strengthening model is another strategy to provide estimations of bulk properties. However, model predictions often use inappropriate obstacle strength factors and superposition methods. In this study, the newly developed nanoindentation protocol, defect-specific strength factors and refined superposition model, were demonstrated on extensive data sets from aged, ion irradiated, and neutron irradiated ferritic/martensitic alloys. This study also addresses the issues in understanding irradiation hardening and provides insight into the fidelity of ion irradiation as a surrogate for neutron irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Characterization, Nuclear Materials |