2017 Annual Meeting

Presentation information

Oral presentation

V. Fusion Energy Engineering » 501-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1B01-07] Irradiated Material Behaviors

Mon. Mar 27, 2017 10:00 AM - 11:55 AM Room B (16-102 Building No.16)

Chair: Yasuhisa Oya (Shizuoka Univ.)

11:00 AM - 11:15 AM

[1B05] Investigtion of irradiation hardening behavior of ion-irradiated F82H by micro-pillar compression test

*Ryuta Kasada1, Riki Simura2, Satoshi Konishi1, Masami Ando3, Hiroyasu Tanigawa3 (1. Institute of Advanced Energy, Kyoto University, 2. Graduate School of Energy Science, Kyoto University, 3. QST)

Keywords:fusion reactor material, irradiation hardening, ion irradiation, micro-pillar compression test

The change in the mechanical strength of a reduced-activation ferritic steel F82H after self ion irradiation was investigated by the micro pillar compression test. The micropillar specimen was fabricated by processing to the ion irradiated sub-surface so as to have a diameter of 1 μm and a height of 2 μm by a focused ion beam processing apparatus. As a result, it was confirmed that the slip deformation in the pillar portion occurred of ion-irradiated
depth region, and the change in compressive strength after the ion irradiation can be obtained.