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  1. 原著論文

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/80896
2a977be6-e945-40aa-9720-48a500e4bc72
Item type 学術雑誌論文 / Journal Article(1)
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.

WEKO 1002682

Alimov, V.Kh.

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Hatano, Y.

× Hatano, Y.

WEKO 1002683

Hatano, Y.

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Kuwabara, T.

× Kuwabara, T.

WEKO 1002684

Kuwabara, T.

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Toyama, T.

× Toyama, T.

WEKO 1002685

Toyama, T.

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Someya, Y.

× Someya, Y.

WEKO 1002686

Someya, Y.

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A.V. Spitsyn

× A.V. Spitsyn

WEKO 1002687

A.V. Spitsyn

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Yoji, Someya

× Yoji, Someya

WEKO 1002688

en 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
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
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