2022 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3H01-06] Irradiation Behavior

Fri. Sep 9, 2022 9:30 AM - 11:00 AM Room H (E1 Bildg.3F No.33)

Chair:Kazutoshi Tokunaga(Kyushu Univ.)

9:30 AM - 9:45 AM

[3H01] Ion irradiation response of cold rolled and recrystallized 12Cr ODS steel

*Jingjie Shen1, Takuya Nagasaka1, Takeo Muroga1, Huilong Yang2, Sho Kano2, Hiroaki Abe2 (1. NIFS, 2. UTokyo)

Keywords:ODS steel, Irradiation defects, Microstructure, Nanoindentation hardness

Oxide-dispersion-strengthened (ODS) steel is regarded as a candidate material in fission and fusion reactors. In this study, to reveal the stability of oxide particles, the microstructure changes of cold rolled and recrystallized 12Cr ODS steel, irradiation experiments with 2.8 MeV Fe2+ were conducted at room temperature (RT) and 673 K. The irradiation dose was in the range of 0.5 ~ 15 dpa. The nanoindentation hardness test and microstructural characterization were carried out. Results showed that the hardness was not evidently changed up to 15 dpa at both RT and 673 K for the cold rolled specimen. By contrast, the hardness of recrystallized specimen was increased with increasing irradiation dose. The hardening mechanisms will be presented.