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Meeting Materials in Nuclear Energy Systems (MiNES) 2025
Symposium Materials in Nuclear Energy Systems (MiNES) 2025
Presentation Title Irradiation Hardening Behavior of Brittele Secondary Phases Formed in Tempered Martensitic Steels
Author(s) Ryuta Kasada, Katsumi Itagaki, Diancheng Geng, Yasuyuki Ogino, Sosuke Kondo, Hao Yu
On-Site Speaker (Planned) Ryuta Kasada
Abstract Scope Tempered martensitic steel (TMS) is expected to serve as a structural material in nuclear systems, including fusion reactors and fast reactors, due to its excellent radiation resistance and mechanical properties. However, the ductile-to-brittle transition behavior inherent in the body-centered cubic (BCC) structure can lead to irradiation embrittlement caused by irradiation hardening. Additionally, brittle fracture is widely recognized to occur when brittle secondary phases (e.g., precipitates) within the material act as crack initiation sites.In our previous studies, the irradiation hardening and deformation behavior of the M23C6 model carbides present in TMS were investigated, demonstrating that M23C6 itself causes irradiation embrittlement.Then, this study investigates the mechanical properties of Fe2M-type Laves phases formed in thermally aged TMS and their changes due to irradiation. Two types of Fe2M laves phases such as Fe2Mo and Fe2W were prepared by arc-melting or powder metallurgy and thermal aging. The obtained specimens were examined by nanoindentation to estimate their indentation modulus and hardness. The potential influence of irradiation hardening of such brittle phases on the irradiation embrittlement of TMS will also be discussed.
Proceedings Inclusion? Undecided

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