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.)

11:15 AM - 11:30 AM

[1B06] Irradiation Hardening Behavior of High-dose Ion Irradiated Reduced Activation Ferritic/Martensitic Steel

*Masami Ando1, Dai Hamaguchi1, Hideo Sakasegawa1, Hiroyasu Tanigawa1, Hironori Kurotaki1 (1. QST Rokkasho Fusion Institute Structural Materials Development Gr)

Keywords:Reduced Activation Ferritic/Martensitic Steel, Irradiation Hardening Behavior, Ion Irradiation

Reduced activation ferritic/martensitic steels (RAFM) are the most promising candidate blanket structural materials for DEMO fusion reactors. The purpose of this study is to summarize the irradiation hardening behavior measured by micro-hardness tests on F82H steels after high-dose ion-irradiation up to 100dpa and compare with the reported data of neutron or ion irradiation.