| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Mechanical Behavior of Structural Materials with Radiation Resistant Microstructures |
| Author(s) |
Thak Sang Byun, Maxim N Gussev, Timothy Lach, Yan-Ru Lin |
| On-Site Speaker (Planned) |
Thak Sang Byun |
| Abstract Scope |
The microstructures of advanced nuclear materials typically include fine grains and nanoparticles to enhance high-temperature strength and radiation resistance. Various processing routes, such as traditional quenching and tempering treatments and additive manufacturing (AM) processes, have been utilized to achieve these microstructures in both ferritic and austenitic materials. This study aims to elucidate the common and distinctive mechanical behaviors of these materials before and after irradiation. Specifically, the research focuses on analyzing the deformation and fracture behaviors of selected materials such as ferritic-martensitic steels, AM stainless steels, and oxide dispersion strengthened (ODS) steels. The goal of the analysis is to identify common microstructural factors contributing to radiation resistance. Furthermore, the study discusses the differences in manufacturing processes and their impact on mechanical performance before and after irradiation, aiming to provide conclusive insights. Additionally, the presentation will introduce a sophisticated alloying technique designed to intentionally modify irradiated microstructures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Iron and Steel |