2019 Annual Meeting

Presentation information

Oral presentation

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

[1O13-17] Fusion Materials (Characteristics)

Wed. Mar 20, 2019 4:05 PM - 5:25 PM Room O (Common Education Bildg. 2 4F No.46)

Chair:Shuhei Nogami(Tohoku Univ.)

4:35 PM - 4:50 PM

[1O15] Evaluation of durability to cyclic heat load and mechanical property of pure tungsten for ITER divertor

*Makoto Fukuda1, Yohji Seki1, Koichiro Ezato1, Hiroshi Nishi1, Kenji Yokoyama1, Satoshi Suzuki1 (1. QST)

Keywords:ITER, Divertor, Tungsten

As part of research for characterizing pure tungsten for ITER divertor with high durability to cyclic heat load, cyclic heat load test with heat flux of 20MW/m2 and mechanical test were performed. Results of these tests and relation between durability to cyclic heat load and mechanical property will be presented.