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タイトル: Surface or bulk He existence effect on deuterium retention in Fe ion damaged W
著者: Oya, Yasuhisa
Sakurada, Shodai
Azuma, Keisuke
Zhou, Qilai
Togari, Akihiro
Kondo, Sosuke
Hinoki, Tatsuya
Yoshida, Naoaki
Buchenauer, Dean
Kolasinski, Robert
Shimada, Masashi
Taylor, Chase N.
Chikada, Takumi
Hatano, Yuji
著者名の別形: 近藤, 創介
檜木, 達也
キーワード: He in damaged W
Hydrogen isotope retention behavior
Damaged W
Fusion
発行日: Aug-2018
出版者: Elsevier BV
誌名: Nuclear Materials and Energy
巻: 16
開始ページ: 217
終了ページ: 220
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.
著作権等: © 2018 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/BY-NC-ND/4.0/).
URI: http://hdl.handle.net/2433/236169
DOI(出版社版): 10.1016/j.nme.2018.06.018
出現コレクション:学術雑誌掲載論文等

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