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.)

10:15 AM - 10:30 AM

[1L03] Experimental study on improvement of material compatibility by using corrosion inhibitor for liquid metal heat transfer mediums of A-FNS irradiation capsule

*Tatsuhiro Hosaka1, Masatoshi Kondo1, Masami Ando2, Satoshi Sato2 (1. Tokyo Tech, 2. QST)

Keywords:Corrosion inhibitor, Liquid lithium, Liquid sodium, Reduced-activation ferritic martensitic steel, Advanced fusion neutron source

Liquid metals Li and Na are candidate heat transfer mediums which are used in irradiation tests in A-FNS. The corrosion characteristics of reduced activation ferritic martensitic steel F82H in the liquid metals should be suppressed to clarify the effect of neutron irradiation on the material properties. The purpose of present study is to investigate the performance of Cr3C2 powder as corrosion inhibitor in the liquid metals. The corrosion tests of F82H in the liquid metals with and without Cr3C2 powder were conducted at 823 K up to 295 hours. The occurrence of corrosion along the boundaries of martensite microstructure in liquid Li was mitigated by the use of the corrosion inhibitor. The carbides precipitated along the boundaries did not chemically react with Li, since the chemical potential of carbon in liquid Li was appropriately adjusted by the addition of Cr3C2 powder. The oxidation corrosion in liquid Na was also mitigated by use of Cr3C2 powder due to the sacrificial reaction of Cr3C2 with oxygen dissolved in liquid Na. The corrosion in liquid Na was promoted due to low carbon potential by adding Mo plate in liquid Na.