2021 Annual Meeting

Presentation information

Oral presentation

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

[2L01-05] Structural Materials 1 (FeCrAlZr-ODS)

Thu. Mar 18, 2021 9:30 AM - 10:55 AM Room L (Zoom room 12)

Chair: Takuya Nagasaka (NIFS)

10:30 AM - 10:45 AM

[2L05] Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts

(5)Excellent corrosion resistance of FeCrAlZr-ODS alloy in high-temperature liquid lead lithium

*Susumu Hatakeyama1, Naoko Oono2, Kan Sakamoto3, Masatoshi Kondo1 (1. Tokyo Tech, 2. Hokkaido Univ., 3. NFD)

Keywords:Fusion reactor, Liquid breeder blanket, Lead Lithium, Corrosion, FeCrAlZr-ODS

Liquid lead lithium alloy (Pb-16Li) is a promising liquid breeder for fusion reactors. The elevation of the blanket temperature enables to promote the energy efficiency and to produce hydrogen. Chemical compatibility of Pb-16Li with structural materials is one of the important issues for the high-temperature operation of liquid Pb-16Li blanket. FeCrAlZr-ODS alloys have been developed. In the present study, corrosion tests of NF-12(Fe-12Cr-6Al-Zr-ODS) in Pb-16Li at 600℃, 750, and 900℃ were performed for 250 hours. NF-12 revealed excellent corrosion resistance even at high temperature due to Al oxide protection layer formed on its surface.