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.)

10:45 AM - 11:00 AM

[1L05] Study on applicability of FeCrAl alloys for liquid metal components in fusion reactors

Mitigation of MHD pressure drop by self-healing oxide layer

*Ryunosuke Nishio1, Masatoshi Kondo1, Teruya Tanaka2, Naoko Oono3 (1. Tokyo Tech, 2. NIFS, 3. Yokohama Natl. Univ. )

Keywords:Fusion reactor, Liquid metal blanket, MHD pressure drop, Magnetohydrodynamics, FeCrAl alloy, Oxide layer

Tritium breeder blankets of fusion reactors play important roles of energy collection, tritium breeding and neutron shielding. MHD pressure drop under magnetic field is one of the important issues to be addressed. FeCrAl alloys are candidates of structural materials for liquid metal components in fusion reactors. They can form α-Al2O3 layer in air at 1273K and LiAlO2 layer in liquid LiPb environment. In present study, the mitigation method of MHD pressure drop by electrical insulation of α-Al2O3 and LiAlO2 formed on FeCrAl alloys was studied. The results of theoretical calculation confirmed that the electrical insulation coating with a thickness of 1μm on inner surface of flow channel sufficiently reduced MHD pressure drop.