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

Research output: Contribution to journalArticlepeer-review

2 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)217-220
Number of pages4
JournalNuclear Materials and Energy
Volume16
DOIs
Publication statusPublished - 2018 Aug

Keywords

  • Damaged W
  • Fusion
  • He in damaged W
  • Hydrogen isotope retention behavior

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science (miscellaneous)
  • Nuclear Energy and Engineering

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