2020 Annual Meeting

Presentation information

Oral presentation

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

[1L01-05] Refractory Structural Materials

Mon. Mar 16, 2020 10:30 AM - 11:55 AM Room L (Lecture Bildg. S 2F S-22)

Chair:Ryuta Kasada(Tohoku Univ.)

11:15 AM - 11:30 AM

[1L04] Recrystallization Behavior, Mechanical Properties, and Irradiation Tolerance of Tungsten-Tantalum Alloys for Fusion Reactor

*Itsuki Ozawa1, Shuhei Nogami1, Takeshi Miyazawa1, Daisuke Asami1, Misako Miwa1, Kiyohiro Yabuuchi2, Akira Hasegawa1 (1. Tohoku.University, 2. Kyoto.University)

Keywords:Fusion reactor, Tungsten alloy, Recrystallization behavior, Mechanical properties, Irradiation tolerance

Low temperature brittleness, recrystallization embrittlement, and neutron irradiation embrittlement are issues of tungsten (W), which is expected for fusion reactor applications. In this presentation, recrystallization behavior, mechanical properties, and irradiation tolerance of tungsten-tantalum (W-Ta) alloys will be reported, which have been developed to overcome those issues.