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 HT9 |
Author(s) |
Benjamin Adam, David Sprouster, Adam Koziol, Luanne Rolly, Caitlin Huotilainen, Julie Tucker |
On-Site Speaker (Planned) |
Benjamin Adam |
Abstract Scope |
Current and future advanced sodium-cooled fast reactor designs demand increased in-service performance of materials used for core and fuel cladding applications. Long-term thermal aging is expected to alter these properties in candidate alloys such as ferritic-martensitic steel HT9. Utilizing computational thermodynamics, macro-mechanical testing, as well as electron microscopy and synchrotron-based characterization approaches, we analyzed the effects of thermal aging (up to 50kh at 360°C - 700°C) on the microstructural properties of HT9. Significant microstructural changes were observed, including matrix grain and M23C6 precipitate growth as well as compositional variations in matrix and precipitates. Decreases in hardness were attributed to matrix grain growth and changes in the precipitate size distribution. Coupling of electron microscopy and synchrotron-based X-ray diffraction results with mechanical property data provides complimentary insight across the multiple length scales needed to fill critical knowledge gaps to predict long-term behavior and performance in these important alloys. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Environmental Effects, Nuclear Materials |