About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
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Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components IV
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Presentation Title |
Microstructure evolution in Alloy 709 following proton irradiation |
Author(s) |
Abhishek Kc, Caleb Massey, Khalid Hattar, Eric Lang |
On-Site Speaker (Planned) |
Abhishek Kc |
Abstract Scope |
Alloy 709 is a strong candidate for use in future nuclear reactors for its excellent compatibility with liquid sodium and creep resistance.
In this study, several samples of Alloy 709 were irradiated with 2.8 MeV proton beam at 0.02, 0.1, and 0.2 dpa to examine the impact of irradiation on Alloy 709. S/TEM techniques identify the radiation-damaged microstructures and a combination of micro- and nano-scale mechanical testing (CSM nanoindentation, micropillar compression, micro-tensile testing) offer direct insights into the effect of the ion irradiation on the mechanical properties. This work, offering small-scale information as a function of local composition and orientation will be compared to on-going meso-scale reduced thickness irradiation-creep experiments.
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Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Iron and Steel |