2016 Annual Meeting

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Oral Presentation

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

[3L09-15] Material Engineering for Fusion Reactor (Low Activation Structural Material)

Mon. Mar 28, 2016 2:45 PM - 4:30 PM Room L (Lecture Rooms C C105)

Chair: Takeo Nishitani (NIFS)

4:15 PM - 4:30 PM

[3L15] Void Swelling Behavior of Multi-Ion Irradiated F82H

＊Masami Ando1, Hiroyasu Tanigawa1, Hironori Kurotaki1 (1.Japan Atomic Energy Agency)

Keywords:Reduced Activation Ferritic/Martensitic Steel, Void Swelling, Ion Irradiation

The purposes of this study are to investigate the void swelling behavior of F82H Mod-3 and BA07 heats after multi-ion-irradiation up to 20dpa and to compare them with that of F82H IEA heat and JLF-1.