2017 Fall Meeting

Presentation information

Oral presentation

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

[2O05-09] Fusion Materials (Corrosion, Mechanical Testing Method)

Thu. Sep 14, 2017 10:35 AM - 12:00 PM Room O (Seminar room 1- Frontier Research in Applied Sciences Building)

Chair:Eiji Hoashi (Osaka Univ.)

10:50 AM - 11:05 AM

[2O06] Experimental study on compatibility of reduced activation ferritic martensitic steel with flowing Pb-17Li

(3)Nanoindentation study on corrosion-erosion dynamics

*Masatoshi Kondo1, Yoshimitsu Hishinuma2, Tanaka Teruya2, Takeo Muroga2, Takayoshi Norimatsu3 (1. Tokyo Institute of Technology, Institute of Inovative Research, Laboratory for Advanced Nuclear Energy, 2. National Institute for Fusion Science, Department of Helical Plasma Research, 3. Osaka university, Institute of Laser Engineering)

Keywords:Liquid blanket, Corrosion

Experimental study on a corrosion of a RAFM steel in a flowing Pb-17Li was performed by means of corrosion tests with a non-isothermal mixing pot apparatus at 773K up to 1000 hours. A nanoindentation analysis was performed on a corroded surface of the tested steels to make clear the dynamic behaviors of corrosion-erosion.