2022 Annual Meeting

Presentation information

Oral presentation

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

[1L01-08] Liquid Metal Engineering in Fusion Reactor

Wed. Mar 16, 2022 9:45 AM - 12:00 PM Room L

Chair: Keisuke Mukai (Kyoto Univ.)

10:30 AM - 10:45 AM

[1L04] Study on applicability of FeCrAl alloys for liquid metal components on fusion reactors

(1)Formation behavior of oxide layer on FeCrAl alloys

*Susumu Hatakeyama1, Yukihiro Miyakawa1, Yoshimitsu Hishinuma2, Masatoshi Kondo1, Teruya Tanaka2, Naoko Oono-Hori3 (1. Tokyo Tech, 2. NIFS, 3. YNU)

Keywords:Fusion reactor, Liquid breeder blanket, Liquid divertor, FeCrAl alloy, Oxide layer

Liquid lead lithium alloy is a candidate tritium breeder of fusion reactors. Liquid metal tin has been proposed as a plasma facing material in liquid divertor concepts. The chemical compatibility is one of the important issues for the development of these in-vessel components. FeCrAl alloys reveal excellent compatibility with the liquid metals because of the formation of protective α-Al2O3 layer by pre-oxidation treatment. The condition of the pre-oxidation treatment should be optimized since the layer properties depend on the temperature and the duration. In the present study, FeCrAl alloys were pre-oxidized at 1173K, 1273K, and 1373K. The adhesion strength of α-Al2O3 layer was evaluated by micro scratch test.