2019 Annual Meeting

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.)

10:00 AM - 10:15 AM

[2O02] Irradiation effects in tungsten materials for fusion reactors

(1)High-temperature tensile properties of neutron-irradiated tungsten materials

*Takeshi Miyazawa1, Lauren M. Garrison2, Yutai Katoh2, Tatsuya Hinoki3, Akira Hasegawa1 (1. Tohoku Univ., 2. Oak Ridge National Laboratory, 3. Kyoto Univ.)

Keywords:Fusion reactor, Divertor, Tungsten, Neutron irradiation, High-temperature tensile properties

In tungsten (W) neutron-irradiated by material testing reactors which have high thermal neutron flux, it is well known that transmutation elements such as rhenium and osmium form irradiation-induced precipitates and then enhance significant irradiation hardening. In this study, we report the high-temperature tensile properties of W materials neutron-irradiated with a thermal neutron shield.