2022 Fall Meeting

Presentation information

Oral presentation

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

[2H10-13] Fusion Material Engineering 1

Thu. Sep 8, 2022 2:45 PM - 3:50 PM Room H (E1 Bildg.3F No.33)

Chair:Makoto Kobayashi(NIFS)

3:15 PM - 3:30 PM

[2H12] Thermal diffusion of hydrogen isotopes under temperature gradient

*Sou Kuramoto1, Terumitsu Ishida1, Kenichi Hashizume1 (1. Kyushu University Interdisciplinary Graduate School of Engineering Sciencs)

Keywords:Thermal Diffusion, Fusion Reactor

Hydrogen isotopes are used as fuel in fusion reactors. In addition, large temperature gradients are assumed in structural materials due to heat recovery and removal. To prevent tritium leakage out of the reactor, it is necessary to evaluate the permeation behavior of hydrogen isotopes in metals under temperature gradients. In this study, deuterium permeation experiments under temperature gradients in metals and alloys were conducted to evaluate the heat of transport Q* of deuterium.