2022 Fall Meeting

Presentation information

Oral presentation

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

[2H14-18] Fusion Material Engineering 2

Thu. Sep 8, 2022 3:50 PM - 5:15 PM Room H (E1 Bildg.3F No.33)

Chair:Naofumi Nakazato(Muroran IT)

4:50 PM - 5:05 PM

[2H18] Electric current induced corrosion of steels in liquid metal at 773 K

*Susumu Hatakeyama1, Masatoshi Kondo1, Naoko Oono2, Teruya Tanaka3 (1. Tokyo Tech, 2. Yokohama Natl. Univ., 3. NIFS)

Keywords:Fusion reactor, Liquid breeder blanket, Liquid divertor, Lithium lead alloy, Electric current induced corrosion

Liquid lithium lead alloy (LiPb) is a candidate liquid breeder of fusion reactors. Liquid tin (Sn) is a candidate coolant of liquid divertor. Electron irradiation of approximately 50 A/cm2 from the plasma may occur in the liquid divertor, and MHD induced current of approximately 100 A/cm2 may occur in the liquid breeder. The effect of electron irradiation and electric current on the material compatibility is an important issue. In the present study, the corrosion tests of 304 and APMT with applying currents of up to 50 A/cm2 in liquid lead and LiPb were performed at 773 K for 250 hours. The corrosion behavior of 304 specimen on the anode was different from that on the cathode.