Blister formation and deuterium retention on tungsten irradiated by low energy and high flux deuterium plasma

K. Tokunaga, M. J. Baldwin, R. P. Doerner, N. Noda, Y. Kubota, N. Yoshida, T. Sogabe, T. Kato, B. Schedler

研究成果: Contribution to conferencePaper査読

1 被引用数 (Scopus)

抄録

Deuterium ion irradiation bas been carried out with incident energies of 100 eV and flux of 1 × 1022 D+m-2s -1 at a temperature in range between 333 K and 1130 K up to a dose of 1 × 1026 D+m-2. Three kinds of tungsten used are pure tungsten made by powder metallurgy tungsten (PM-W), vacuum plasma spray tungsten (VPS-W) and single crystal tungsten (SC-W). Surface morphology before and after the irradiation is observed with a SEM. Retention property of deuterium after the irradiation is also examined with a TDS. Blisters with a diameter of about 0.2-2.0 μ m are formed on PM-W by deuterium irradiation at 333 K and 673 K but size and shape of those blisters change depending on the irradiation temperatures. However, no blisters are found on PM-W at elevated temperatures between 723 and 1130 K. On the other hand, blisters with a diameter of about 2 μ m are formed on SCW irradiated at 343 K but no blisters are observed on SCW irradiated at 383, 623 and 1123 K. In the case of VPS-W irradiated at 333, 723 and 1123 K, modification like blister with a diameter of about 0.2 μ m occurs. TDS measurement also shows that deuterium is not retained in sample, which the blisters are not formed.

本文言語英語
ページ242-245
ページ数4
出版ステータス出版済み - 2003
イベント20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03 - San Diego, CA, 米国
継続期間: 10 14 200310 17 2003

その他

その他20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03
国/地域米国
CitySan Diego, CA
Period10/14/0310/17/03

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Blister formation and deuterium retention on tungsten irradiated by low energy and high flux deuterium plasma」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