Deuterium retention in deposited W layer exposed to EAST deuterium plasma

K. Katayama, N. Ashikawa, F. Ding, H. Mao, H. S. Zhou, G. N. Luo, J. Wu, M. Noguchi, S. Fukada

研究成果: ジャーナルへの寄稿学術誌査読

5 被引用数 (Scopus)

抄録

The deposited W layers formed on the W plate by hydrogen plasma sputtering were exposed to deuterium plasma in EAST together with bare W plate. In TDS measurement, the deuterium release was clearly observed from the deposited W layer in addition to the release of hydrogen which was incorporated during the sputtering-deposition processes. On the other hand, the release of hydrogen isotope was not detected from the bare W plate. This suggests that the formation of deposited W layers increases tritium inventory in the plasma confinement vessel. Although the thermocouple contacting to the backside of the W plate did not indicate a remarkable temperature rise, deuterium release peaks from the W layer were close to that from the W layer irradiated by 2 keV D2 + at 573 K. It was found by glow discharge optical emission spectrometry analysis that retained deuterium in the W layer has a peak at the depth of 50 nm and gradually decreases toward the W substrate. From X-ray photoelectron spectroscopy analysis, it was evaluated that W oxide existed just at the surface and W atoms in the bulk of deposited W layer were not oxidized. These data suggest that hydrogen isotopes are not retained in W oxide but grain boundaries.

本文言語英語
ページ(範囲)617-621
ページ数5
ジャーナルNuclear Materials and Energy
12
DOI
出版ステータス出版済み - 8月 2017

!!!All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(その他)
  • 原子力エネルギーおよび原子力工学

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