2016 Annual Meeting

Presentation information

Oral Presentation

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

[3L01-04] Tritium breeders and neutron multiplier (Fabrication technology and chemical characteristics)

Mon. Mar 28, 2016 9:50 AM - 10:55 AM Room L (Lecture Rooms C C105)

Chair: Takumi Chikada (Shizuoka Univ.)

10:35 AM - 10:50 AM

[3L04] Experimental study on compatibility of reduced activation ferritic martensitic steel with flowing Pb-17Li

Metallurgical analysis of corrosion-erosion part of steel surface and discussion on corrosion-erosion mechanism

*Masatoshi Kondo1, Yoshimitsu Hishinuma2, Takeo Muroga2 (1.Tokyo Institute of Technology, Research Laboratory for Nuclear Reactors, 2.National Institute for Fusion Science, Department of Helical Plasma Research )

Keywords:Liquid blanket, Compatibility, Reduced activation ferritic martensitic steel

非等温型攪拌装置を用いて、流動鉛リチウム環境下における低放射化フェライト鋼の共存性を調べた。鋼材表面のコロージョン・エロージョン箇所の詳細分析を実施し、その結果に基づきコロージョン・エロージョン発生機構を検討した。