2023 Fall Meeting

Presentation information

Oral presentation

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

[2L08-12] Structural Materials for Nuclear Fusion Reactors 1

Thu. Sep 7, 2023 2:45 PM - 4:05 PM Room L (ES Bildg. 3F ES033)

Chair:Akira Hasegawa(Tohoku Univ.)

3:30 PM - 3:45 PM

[2L11] Ion irradiation effects on the 12Cr ODS steel after a novel recrystallization process

*Jingjie Shen1, Takeo Muroga1, Kiyohiro Yabuuchi2, Sho Kano3, Hiroaki Abe3 (1. NIFS, 2. Kyoto Univ., 3. UTokyo)

Keywords:ODS steel, Ion irradiation, irradiation defects, Hardening

A multi-directional thermomechanical process was applied to get recrystallization and thus improve the ductility of oxide dispersion strengthened (ODS) ferritic steel. In this study, it is to investigate the microstructural evolution and hardness changes of the recrystallized 12Cr ODS steel upon ion irradiation. Ion irradiation experiments were carried out at 973 K using single beam (6.4 MeV Fe3+) and dual beam (6.4 MeV Fe3+ and 1 MeV He+). Irradiation dose was estimated at about 10.5 dpa at the peak damage. After irradiation, the nanoindentation harness tests were conducted, and microstructure was characterized by TEM. Results showed that irradiation defects such as helium bubbles were observed, however, the irradiation hardening was not obvious, suggesting helium bubbles did not evidently induce hardening.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password