About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
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Presentation Title |
Structure-property Relationships in Long-term Thermally Aged T91 and T92 |
Author(s) |
Caitlin Huotilainen, Benjamin Adam, Adam Koziol, David Sprouster, Luanne Rolly, Julie Tucker, Natan Beets |
On-Site Speaker (Planned) |
Natan Beets |
Abstract Scope |
Materials for fuel cladding and core applications in sodium-cooled fast reactors are expected to experience a high temperature and demanding environment for extended times. Understanding the long-term thermal stability of candidate ferritic-martensitic steels, such as Grade 91 and Grade 92, is critical for material qualification. In this work, plates of Grade 91 and Grade 92 were isothermally aged up to 10kh, 30kh and 50kh at 360°C, 500°C, 600°C and 700°C, then characterized using electron microscopy, synchrotron based and mechanical testing characterization techniques to evaluate the effects of thermal aging on microstructural and mechanical evolutions. Variations in grain size, grain morphology, grain boundary character, precipitate type and size distribution were quantified and correlated with mechanical test results. These results, coupled with mechanical property data, provide complimentary insight across multiple length scales. This is needed to enable prediction on long-term material behavior in sodium-cooled fast reactor applications. |
Proceedings Inclusion? |
Planned: |
Keywords |
Environmental Effects, Characterization, Nuclear Materials |