2022 Fall Meeting

Presentation information

Oral presentation

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

[2H01-03] F82H

Thu. Sep 8, 2022 9:30 AM - 10:20 AM Room H (E1 Bildg.3F No.33)

Chair:Makoto Oyaidzu(QST)

10:00 AM - 10:15 AM

[2H03] Fretting corrosion behaviors of Li2.15TiO3 pebble and RAFM steel F82H under inert gas environment

*Haruya Masaki1, Masatoshi Kondo1, Jae-Hwan Kim2, Masaru Nakamichi2, Masami Ando2, Taehyun Hwang2, Yutaka Sugimoto2 (1. Tokyo Tech, 2. QST)

Keywords:Fusion reactor, Fretting corrosion, Blanket, Solid breeder, RAFM steel

Fretting corrosion can be induced between tritium breeder pebbles and coolant tubes vibrated due to the coolant flow in the solid breeder blanket of fusion reactors. The purpose is to clarify the fretting corrosion behaviors of tritium breeder pebble and reduced activation ferritic martensitic steel under the condition simulating the fusion blanket. The pebbles of Li2TiO3 with excess Li (Li2.15TiO3) were produced by emulsion method. The fretting tests between the pebble of Li2.15TiO3 and the plate of F82H were conducted at 573 K in the argon environment containing 1 vol% oxygen. The surface of F82H specimen was oxidized at 573 K and became harder. The harder surface revealed the resistance to the fretting corrosion.