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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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