2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2G01-06] Themal System

Wed. Mar 27, 2024 9:30 AM - 11:00 AM Room G (21Bildg.3F 21-317)

Chair:Keisuke Mukai(Kyoto Univ.)

10:30 AM - 10:45 AM

[2G05] Chemical compatibility of liquid metals with structural material under stress loading conditions

*Kenshi Ohno1, Masatoshi Kondo1, Naoko Oono2 (1. Tokyo Tech, 2. Yokohama Natl. Univ.)

Keywords:316L austenitic steel, Liquid lead lithium, Liquid tin, Fusion reactor, Liquid divertor, Liquid blanket, Corrosion, Stress

Liquid metal LiPb and Sn are promising liquid breeder and divertor of fusion reactor. Stress is applied to structural materials by an electromagnetic force in magnetic confinement fusion reactors. The effect of stress applied on the chemical compatibility has been rarely clarified so far. The corrosion tests were performed in the liquid metals at static condition with C-ring specimens which had an outer diameter of 35 mm. The maximum tensile stress applied in the C-ring specimens according to their elastic deformation by a bolt tightening method was up to 200 MPa. The test duration was up to 1000 hours and the test temperature was up to 773 K. The corrosion was not promoted by the applied stress significantly though that was done by the temperature.

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