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)

3:45 PM - 4:00 PM

[2G15] Development of potassium doped tungsten thick plates for fusion reactors

(1) Overview of R&D and effectiveness of potassium doping

*Shuhei Nogami1, Akira Hasegawa2, Naoya Matsuta1, Kei Miura1, Shigekazu Yamazaki1, Seiji Nakabayashi1, Tomohiro Takida1 (1. A.L.M.T., 2. Tohoku Univ.)

Keywords:Tungsten, Potassium doping, Low-temperature brittleness, Recrystallization embrittlement, Neutron irradiation embrittlement

Tungsten material used in fusion DEMO and beyond requires the improvement of low-temperature brittleness and suppression of recrystallization embrittlement and neutron irradiation embrittlement. In this study, potassium-doped tungsten plates with an appropriate thickness of fusion reactor divertors have been developed, which can overcome these issues. In this presentation, the overview of R&D, especially focusing on the effectiveness of potassium doping in addressing these issues, will be reported.

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

Password