Suppression of blister formation and deuterium retention on tungsten surface due to mechanical polishing and helium pre-exposure

D. Nishijima, H. Iwakiri, K. Amano, M. Y. Ye, N. Ohno, K. Tokunaga, N. Yoshida, S. Takamura

研究成果: ジャーナルへの寄稿学術誌査読

54 被引用数 (Scopus)

抄録

Low-energy deuterium (D) plasma exposure on tungsten (W), which is an important material for ITER, results in blister formation on the surface. Blister formation increases both micron-sized dust production and D retention. Blister formation depends greatly on surface pre-treatment. Deuterium plasma exposure on mirror-finished powder metallurgy W at 500 K for 3 h forms a blister with a diameter of a few hundred micrometres on the surface. Blister formations on the mechanically-polished and helium-pre-exposed surfaces are drastically suppressed. Deuterium retention is also reduced on both the mechanically- polished surface and the helium-pre-exposed surface compared with that on the mirror-finished surface. The suppressive effect of blister formation on the mechanically-polished surface is maintained for 50 h. The size of blisters and D retention on mirror-finished surface exposed for 50 h increases by some degrees (≲500 νm, 7 × 1020 m-2) compared with that on mirror-finished surface exposed for 3 h (≲200 νm, 5 × 10 20 m-2), but is not proportional to the exposure time. The saturation level of D retention even on blister-rich surfaces seems to be lower than an order of 1021 D2 m-2.

本文言語英語
ページ(範囲)669-674
ページ数6
ジャーナルNuclear Fusion
45
7
DOI
出版ステータス出版済み - 7月 1 2005

!!!All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 凝縮系物理学

フィンガープリント

「Suppression of blister formation and deuterium retention on tungsten surface due to mechanical polishing and helium pre-exposure」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル