Surface or bulk He existence effect on deuterium retention in Fe ion damaged W

Yasuhisa Oya, Shodai Sakurada, Keisuke Azuma, Qilai Zhou, Akihiro Togari, Sosuke Kondo, Tatsuya Hinoki, Naoaki Yoshida, Dean Buchenauer, Robert Kolasinski, Masashi Shimada, Chase N. Taylor, Takumi Chikada, Yuji Hatano

研究成果: Article査読

3 被引用数 (Scopus)

抄録

To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced into W bulk by 201 – 1000 keV He+, or W surface by 3 keV He+ for 6 MeV Fe ion damaged W at room temperature. The deuterium (D) retention behavior was evaluated by thermal desorption spectroscopy (TDS). In addition, the amount of tritium (T) at surface and bulk were separately evaluated by beta-ray induced X-ray spectroscopy (BIXS). The experimental results indicated that the formation of He-void complexes reduced the D trapping in vacancies and voids which have higher trapping energy by the bulk He retention. The BIXS measurement also supported the He enhanced the D reduction in the W bulk region. On the other hand, the He ion irradiation near the surface region enhanced D trapping by dislocation loops or surface, indicating the existence of He near surface interfered the D diffusion toward the bulk. It was concluded that the He existence in bulk or surface will significantly change the D trapping and diffusion behavior in damaged W.

本文言語English
ページ(範囲)217-220
ページ数4
ジャーナルNuclear Materials and Energy
16
DOI
出版ステータスPublished - 2018 8
外部発表はい

ASJC Scopus subject areas

  • 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

フィンガープリント

「Surface or bulk He existence effect on deuterium retention in Fe ion damaged W」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