2022 Fall Meeting

Presentation information

Oral presentation

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

[3H07-10] Heat Load Testing of Divertor Materials

Fri. Sep 9, 2022 11:00 AM - 12:00 PM Room H (E1 Bildg.3F No.33)

Chair:Akira Hasegawa(Tohoku Univ.)

11:00 AM - 11:15 AM

[3H07] Investigation of thermal property of W-SiC/SiC joints under high heat load using ACT2

*Hiroya Ise1, Naofumi Nakazato1, Yukinori Hamaji2, Jingjie Shen2, Hirotatsu Kishimoto1 (1. Muroran IT, 2. NIFS)

Keywords:divertor, tungsten, SiC/SiC composite, high heat load stability, microstructure

A SiC/SiC composite is expected to be a candidate structural material for the plasma-facing components after DEMO reactors. The tungsten coated SiC/SiC composite (W-SiC/SiC) is one of the divertor designs. Investigation of high heat load effects and the thermal stabilities of W-SiC/SiC joints are limited. The ACT2 at the National Institute for Fusion Science (NIFS), Japan is a facility for high heat load tests using the electron beam irradiation. The experience of high heat load test of ceramics composite and its joints at ACT2 is limited. The objectives of this research are to develop the method by the combination of experimental data at ACT2 and a FEM analysis, and evaluate the thermal properties of W-SiC/SiC under high heat load introduction.