About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
Deformation Mechanisms in Gen-IV Candidate Structural Steels Studied by In-situ Micromechanical Testing Techniques |
Author(s) |
Tanvi Ajantiwalay, Cheng-Han Li, Tingkun Liu, Christopher San Marchi, Assel Aitkaliyeva, Arun Devaraj |
On-Site Speaker (Planned) |
Tanvi Ajantiwalay |
Abstract Scope |
Austenitic and ferritic/martensitic steels are extensively researched for their use as structural materials in advanced Gen-IV reactors. Constant exposure to the extreme reactor environments such as constant stresses and temperatures, however, can degrade their mechanical properties. The main goal of this study is to understand the deformation mechanisms of 316 and HT-9 steels using in-situ micromechanical techniques such as nanoindentation, micro-pillar compression and micro-tensile testing. The results show that for 316, a mechanical anisotropy exists between different crystal orientations and the deformation occurs via slip along the closely packed planes. The transmission electron microscopy of the deformed surfaces reveals the formation of nano-twins in the slipped region. HT-9, however, shows slipping along the lath boundaries and the failure mechanisms are largely dependent on their microstructural features. Such a specific deformation-based study of these steels will help create a baseline to further estimate their overall behavior in the actual reactor environments. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Mechanical Properties, Characterization |