2018 Fall Meeting

Presentation information

Oral presentation

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

[2N13-15] Behavior of Hydrogen Isotope in Fusion Materials

Thu. Sep 6, 2018 3:50 PM - 4:40 PM Room N (D23 -D Building)

Chair:Yasuhisa Oya(Shizuoka Univ.)

4:05 PM - 4:20 PM

[2N14] Deuterium permeation behavior through reduced activation ferritic steel F82H under DEMO reactor blanket condition

*Keisuke Kimura1, Jumpei Mochizuki1, Seira Horikoshi1, Moeki Matsunaga1, Hikari Fujita2, Kouhei Okitsu2, Yoshiteru Sakamoto3, Youji Someya3, Hirofumi Nakamura3, Takumi Chikada1 (1. Graduate school of Integrated Science and Technology, Shizuoka University , 2. The University of Tokyo, 3. National Institutes for Quantum and Radiological Science and Technology)

Keywords:Reduced activation ferritic steel, Hydrogen, Permeation

Hydrogen isotope permeation behaviors in reduced activation ferritic/martensitic (RAFM) steels have been investigated. In this study, deuterium permeation through the RAFM steels heat-treated under simulated environmental conditions has been investigated for more precise prediction of tritium migration at fusion reactor blankets. In the results, the formed oxide layers suppressed deuterium permeation to approximately 1/4.