2024 Annual Meeting

Presentation information

Oral presentation

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

[2G01-06] Themal System

Wed. Mar 27, 2024 9:30 AM - 11:00 AM Room G (21Bildg.3F 21-317)

Chair:Keisuke Mukai(Kyoto Univ.)

10:45 AM - 11:00 AM

[2G06] Chemical compatibility of Zr alloy and Ti alloy in liquid Sn environment

*Sota Hagiwara1, Kan Sakamoto2, Masatoshi Kondo1 (1. Tokyo Tech, 2. NFD)

Keywords:Fusion reactor, Liquid Sn, Compatibility, Zr alloy, Ti alloy, Oxide layer

The compatibility of structural materials with liquid Sn is one of the important issues for the development of liquid Sn divertors of fusion reactors. The purpose is to clarify the chemical compatibility of Zry4 (Zr-1.33Sn-0.21Fe-0.12Cr-0.13O) and 64Ti (Ti-6.3Al-4.1V) with liquid Sn. The specimens were pre-oxidized in high-temperature air to form protective oxide layers, and they were immersed to liquid Sn at 500℃ for 250 hours. The specimens after the corrosion tests were cleaned with nitric acid solution. The mass increase of the specimens was recognized. The mass increase of the pre-oxidized Zry4 was small as 22.5 g/m2 since the ZrO2 layer could function to suppress the alloying corrosion in liquid Sn.

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