2019 Annual Meeting

Presentation information

Oral presentation

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

[1O08-12] Development of Tungsten Alloys and Composites

Wed. Mar 20, 2019 2:45 PM - 4:05 PM Room O (Common Education Bildg. 2 4F No.46)

Chair:Tatsuya Hinoki(Kyoto Univ.)

3:30 PM - 3:45 PM

[1O11] Development of Tungsten Alloys and Composites for Fusion Reactor

(4) Damage Formation Behavior of Dispersion-strengthened Tungsten Alloys by Thermal Shock Loads

*Kento Matsui1, Shuhei Nogami1, Gerald Pintsuk2, Marius Wirtz2, Thorsten Loewenhoff2, Akira Hasegawa1 (1. Tohoku Univ., 2. FZJ)

Keywords:Fusion reactor, Tungsten, Dispersion-strengthening, Alloying, Thermal shock

To improve both mechanical properties and recrystallization resistance, tungsten alloys, which are disperson-strengthened by potassium bubbles and lanthanum oxide and alloyed by rhenium, have been developed. In the presentation (4), we will show the damage formation behavior of dispersion-strengthened tungsten alloys by thermal shock loads.