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  1. 原著論文

Effect of helium irradiation on deuterium permeation behavior in tungsten

https://repo.qst.go.jp/records/48991
https://repo.qst.go.jp/records/48991
a36bb4d3-3fae-420c-b9bb-4d478e700d03
Item type 学術雑誌論文 / Journal Article(1)
公開日 2018-05-15
タイトル
タイトル Effect of helium irradiation on deuterium permeation behavior in tungsten
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 Uemura, Yuki

× Uemura, Yuki

WEKO 494009

Uemura, Yuki

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Sakurada, Shodai

× Sakurada, Shodai

WEKO 494010

Sakurada, Shodai

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Fujita, Hiroe

× Fujita, Hiroe

WEKO 494011

Fujita, Hiroe

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Keisuke, Azuma

× Keisuke, Azuma

WEKO 494012

Keisuke, Azuma

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Zhou, Quilai

× Zhou, Quilai

WEKO 494013

Zhou, Quilai

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Hatano, Yuji

× Hatano, Yuji

WEKO 494014

Hatano, Yuji

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Yoshida, Naoaki

× Yoshida, Naoaki

WEKO 494015

Yoshida, Naoaki

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Watanabe, Hideo

× Watanabe, Hideo

WEKO 494016

Watanabe, Hideo

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小柳津, 誠

× 小柳津, 誠

WEKO 494017

小柳津, 誠

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磯部, 兼嗣

× 磯部, 兼嗣

WEKO 494018

磯部, 兼嗣

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Shimada, Masashi

× Shimada, Masashi

WEKO 494019

Shimada, Masashi

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Buchenauer, Dean

× Buchenauer, Dean

WEKO 494020

Buchenauer, Dean

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Kolasinski, Robert

× Kolasinski, Robert

WEKO 494021

Kolasinski, Robert

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Chikada, Takumi

× Chikada, Takumi

WEKO 494022

Chikada, Takumi

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小柳津 誠

× 小柳津 誠

WEKO 494023

en 小柳津 誠

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磯部 兼嗣

× 磯部 兼嗣

WEKO 494024

en 磯部 兼嗣

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抄録
内容記述タイプ Abstract
内容記述 In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He+ was approximately one order of magnitude lower than that for un-damaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for un-damaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability and diffusion coefficients return to levels observed for undamaged material. It is possible that these effects are linked to annealing of defects introduced by ion damage, and whether the defects are stabilized by the presence of trapped He.
書誌情報 Journal of Nuclear Materials

巻 490, p. 242-246, 発行日 2017-07
DOI
識別子タイプ DOI
関連識別子 10.1016/j.jnucmat.2017.04.041
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