Irradiation effects in tungsten materials for fusion reactors

Yusuke Sato

Presentation information

Oral presentation

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

[2O01-04] Tungsten(Radiation Effects)

Thu. Mar 21, 2019 9:45 AM - 10:50 AM Room O (Common Education Bildg. 2 4F No.46)

Chair:Yoshitaka Matsukawa(Tohoku Univ.)

10:30 AM - 10:45 AM

[2O04] Irradiation effects in tungsten materials for fusion reactors

(3) Microstructure and high-temperature tensile properties of helium-implanted tungsten

*Yusuke Sato¹, Daichi Ito¹, Takaya Hattori¹, Takeshi Miyazawa¹, Shuhei Nogami¹, Akira Hasegawa¹ (1. Tohoku Univ.)

Keywords:Fusion reactor, Tungsten, Helium implantation, Microstructure, High-temperature tensile properties

Tungsten (W) is expected to generate about 20 appm of helium (He) by the nuclear transmutation reaction with high energy neutrons. In this study, we report microstructural development and high-temperature tensile properties of W implanted 20 appm of He from recovery to recrystallization by using the post-irradiation annealing up to 1500℃.