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)

3:30 PM - 3:45 PM

[3L12] Tensile properties for ion-irradiated F82H steel by micro-tensile testing

＊Terumitsu Miura1, Katsuhiko Fujii1, Koji Fukuya1, Masami Ando2, Hiroyasu Tanigawa2 (1.Institute of Nuclear Safety System, 2.Japan Atomic Energy Agency)

Keywords:Reduced Activation Ferritc/Martensitic Steel, Micro-tensile testing, Ion irradiation, Tensile property, Radiation effect

Fe/Heイオン照射したF82H鋼に室温で超微小引張試験を実施した結果，照射による降伏応力の増加と伸びの減少が確認された。本試験法が引張特性に及ぼす照射影響の評価手法として有効であることを確認した。