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Tungsten samples, undamaged and neutron-irradiated to a damage level of approximately 0.016 displacements per atom, are exposed to low-energy (108 eV), high-flux (3.0 × 1021 to 9.4 × 1021 m−2 s−1) deuterium plasma at temperatures ranging from 573 to 773 K to an ion fluence of 1.1 × 1025 m−2. At each exposure temperature, two undamaged and two neutron-irradiated tungsten samples are exposed to plasma. The deuterium content in the tungsten samples is measured by thermal desorption spectrometry soon after the plasma exposure and after post-plasma annealing at 573 K for 30 h. 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Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing
https://repo.qst.go.jp/records/80896
https://repo.qst.go.jp/records/808962a977be6-e945-40aa-9720-48a500e4bc72
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2020-11-05 | |||||
タイトル | ||||||
タイトル | Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Alimov, V.Kh.
× Alimov, V.Kh.× Hatano, Y.× Kuwabara, T.× Toyama, T.× Someya, Y.× A.V. Spitsyn× Yoji, Someya |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | We examine the effect of neutron irradiation on the release of deuterium from tungsten at 573 K to understand the efficiency of tritium removal by baking out at moderate temperatures. Tungsten samples, undamaged and neutron-irradiated to a damage level of approximately 0.016 displacements per atom, are exposed to low-energy (108 eV), high-flux (3.0 × 1021 to 9.4 × 1021 m−2 s−1) deuterium plasma at temperatures ranging from 573 to 773 K to an ion fluence of 1.1 × 1025 m−2. At each exposure temperature, two undamaged and two neutron-irradiated tungsten samples are exposed to plasma. The deuterium content in the tungsten samples is measured by thermal desorption spectrometry soon after the plasma exposure and after post-plasma annealing at 573 K for 30 h. It is found that: (i) the deuterium retention in the neutron-irradiated tungsten samples is significantly higher than that in the undamaged tungsten samples; (ii) annealing at 573 K of undamaged tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to an almost complete (60%–99%) release of deuterium from the samples; (iii) annealing at 573 K of neutron-irradiated tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to a significant (8%–20%) release of deuterium from the samples. | |||||
書誌情報 |
Nuclear Fusion 巻 60, 号 9, p. 096025, 発行日 2020-11 |
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出版者 | ||||||
出版者 | IOP Publishing | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0029-5515 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1088/1741-4326/aba337 | |||||
関連サイト | ||||||
識別子タイプ | URI | |||||
関連識別子 | https://iopscience.iop.org/article/10.1088/1741-4326/aba337 |