| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
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| Presentation Title |
Fracture Toughness of F82H Steel after Neutron Irradiation to ~70 dpa at 400°C and 500°C |
| Author(s) |
Xiang (Frank) Chen, Mikhail Sokolov, Takashi Nozawa, Masami Ando, Dai Hamaguchi, Josina W Geringer, Hiroyasu Tanigawa, Yutai Katoh |
| On-Site Speaker (Planned) |
Xiang (Frank) Chen |
| Abstract Scope |
F82H is the reference reduced activation ferritic/martensitic steel for fusion reactor designs in Japan. This study involved fracture toughness testing of two F82H steels, the IEA and Mod3 heats, neutron irradiated at the High Flux Isotope Reactor of Oak Ridge National Laboratory. The target irradiation temperatures were 400°C and 500°C with a fluence of ~70 displacements per atom (dpa). Evaluation of SiC temperature monitors indicated the median irradiation temperatures were close to 394°C and 473°C. Vickers microhardness tests revealed a 15 to 35HV increase in microhardness for the 394°C irradiation while no hardening was measured for the 473°C irradiation, matching the expected irradiation temperature effect. In addition, fracture toughness analysis based on the ASTM E1921 Master Curve method indicated moderate irradiation embrittlement, i.e., 32-58°C increase in the Master Curve reference temperature T0 for the 394°C irradiation and 18-43°C increase in T0 for the 473°C irradiation, for both materials. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Environmental Effects |