2024 Annual Meeting

Presentation information

Oral presentation

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

[2G11-16] Functional Material

Wed. Mar 27, 2024 2:45 PM - 4:20 PM Room G (21Bildg.3F 21-317)

Chair:Naoko Ashikawa(Kyoto Fusioneering)

2:45 PM - 3:00 PM

[2G11] Evaluation of Deuterium Absorption/Desorption Behavior on Graphite -Effects of Metal Impurities on Deuterium Desorption Behavior from Carbon Dust-

*RYOICHI YAMAMOTO1, Hisao Atsumi1 (1. Kindai Univ.)

Keywords:Graphite, carbon dust, deuterium absorption/desorption, PFC, mechanical alloying, TDS

When graphite is used in a fusion reactor plasma facing wall (PFC), carbon dust should form on the surface of the PFC and its tritium inventory cause a problem. However, the carbon dust coexisting with metal impurities is considered to have an effect on the retention/desorption of hydrogen isotopes. In this study, deuterium desorption behavior from carbon dust coexisting with metal impurities was measured. Starting material was isotropic graphite (IG-430U), and metal impurities were Fe, Cr, and Ni. These were milled by mechanical alloying in a deuterium atmosphere to simulate carbon dust, and desorption spectra were measured with a TDS. The retention decreased in the sample coexisting with Cr, indicating that the spectra change was caused by metal impurities.