| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Metals and Ceramics
|
| Presentation Title |
Radiation Response of Grade 92 Ferritic-martensitic Steel Irradiated up to 14.63 dpa at ~700°C |
| Author(s) |
Weicheng Zhong, Lizhen Tan |
| On-Site Speaker (Planned) |
Weicheng Zhong |
| Abstract Scope |
Ferritic-martensitic steel Grade 92 is a candidate structural material for Gen-IV nuclear reactors. In contrast to the irradiation studies generally conducted at 300–600°C, this study reports the evolution of microstructures and mechanical properties of Grade 92 irradiated up to 14.63 displacements per atom (dpa) at ~700°C in the High Flux Isotope Reactor of Oak Ridge National Laboratory. Room temperature tensile test and Vickers hardness measurement were performed to evaluate mechanical property evolution after 0.46, 7.44, and 14.63 dpa irradiations. Microstructural characterization using transmission electron microscopy, coupled with energy dispersive x-ray spectroscopy and electron backscatter diffraction, manifested the primary evolution of grain structure and precipitates. The virgin and 700°C-aged Grade 92 samples were evaluated in parallel as references for the irradiated samples to better understand the irradiation effect on the microstructure and mechanical property evolution at ~700°C. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |