2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-4 Reactor Component Technology, First Wall, Divertor, Magnet

[3G10-15] Fusion Reactor Components

Thu. Mar 28, 2024 2:45 PM - 4:20 PM Room G (21Bildg.3F 21-317)

Chair:Masatosh Kondo(Tokyo Tech)

3:30 PM - 3:45 PM

[3G13] Reconsideration of heat conduction in plasma irradiated complex metal target

*Hiroto Matsuura1, Son Xuan Nhat Bui1, Mizuki Sakamoto2 (1. Osaka Metropolitan University, 2. University of Tsukuba)

Keywords:divertor target material, heat conduction model, helicon plasma

We had conducted helicon plasma irradiation test onto tangsten/cupper composite target, which was the candidate for the divertor plate. At that time, temperature evolution measured by IR camera and thermocouples could not be well explained. By using recently developed heat conduction model for long time heat flux sensor, it is confirmed that temperature distribution in the target and irradiation surface temperature can be explained. In this work, this irradiation test is reconsidered.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password