2022 Annual Meeting

Presentation information

Oral presentation

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

[1L09-13] Tritium Breeder and Coating Technique

Wed. Mar 16, 2022 2:45 PM - 4:15 PM Room L

Chair: Makoto Kobayashi (NIFS)

3:15 PM - 3:30 PM

[1L11] Study on fretting corrosion in solid breeder blanket

*Haruya Masaki1, Masatoshi Kondo1, Jae-Hwan Kim2, Masaru Nakamichi2 (1. Tokyo Tech, 2. QST)

Keywords:fretting corrosion, Li2TiO3, F82H, RAFM, oxide layer

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 occurrence of the fretting corrosion degrades the mechanical integrity and finally severe incidents. Therefore, the behavior of fretting corrosion must be clarified. In the present study, fretting tests between lithium titanate (Li2TiO3) pebbles and reduced activation ferritic/martensitic steel F82H specimen were conducted for 10min at room temperature, 100, 200 and 300℃ under air atmosphere. After the fretting tests, the fretting scar of the specimen and Li2TiO3 pebbles were analyzed using SEM, EDS, and 3D laser scanning microscope. The fretting debris produced by the fretting corrosion was also analyzed. The fretting corrosion tests with FeCrAl alloy APMT were performed and its excellent resistance was clearly recognized.