About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
Microstructure and Mechanical Properties of Neutron Irradiated Tantalum-alloyed Ferritic Martensitic Steels |
Author(s) |
Weicheng Zhong, Lizhen Tan, Thak Sang Byun, Ying Yang |
On-Site Speaker (Planned) |
Weicheng Zhong |
Abstract Scope |
Castable nanostructured alloys (CNAs) are being developed in ORNL as American reduced activation ferritic martensitic steels for the first wall/blanket applications in fusion reactors. One of the early generation (tantalum-alloyed) CNAs has been irradiated in High Flux Isotope Reactor at temperatures up to ~650℃ to damage doses of ~0.5 - 9 dpa. Vickers microhardness and tensile tests were performed at room temperature, and they reveal consistent hardening or softening depending on the irradiation temperature. Irradiation induced hardening was observed at the irradiation temperature of 400℃, and softening at >490℃. Microstructures in irradiated samples were characterized to understand the post-irradiation mechanical behaviors. SEM-EBSD is used to trace the grain structure evolution, and TEM is used to investigate the irradiation induced defects and precipitates stability. The microstructural changes will be correlated to understand the tensile behaviors after irradiation. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Iron and Steel, |