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Water Corrosion behavior of RAFM and Cu-alloy for Japanese DEMO component

https://repo.qst.go.jp/records/83953
https://repo.qst.go.jp/records/83953
cc87b9c5-b9ff-4e94-b351-9273d8963136
Item type 会議発表用資料 / Presentation(1)
公開日 2021-11-25
タイトル
タイトル Water Corrosion behavior of RAFM and Cu-alloy for Japanese DEMO component
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_c94f
資源タイプ conference object
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 Motoki, Nakajima

× Motoki, Nakajima

WEKO 1014239

Motoki, Nakajima

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Huang, Yenjui

× Huang, Yenjui

WEKO 1014240

Huang, Yenjui

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Takashi, Nozawa

× Takashi, Nozawa

WEKO 1014241

Takashi, Nozawa

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Motoki, Nakajima

× Motoki, Nakajima

WEKO 1014242

en Motoki, Nakajima

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Huang, Yenjui

× Huang, Yenjui

WEKO 1014243

en Huang, Yenjui

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Takashi, Nozawa

× Takashi, Nozawa

WEKO 1014244

en Takashi, Nozawa

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抄録
内容記述タイプ Abstract
内容記述 The water-cooled system using high-temperature pressurized water is a primary candidate for the blanket and divertor of the Japanese fusion DEMO reactor. Both reduced activation ferritic/martensitic steel (RAFM) (for blanket and divertor) and the copper alloy (for divertor) are used as the key structure of cooling pipes. The water chemistry of these systems needs to be decided based on the corrosion behavior of these materials, especially depending on the dissolved oxygen (DO) level. This study aims to summarize the evaluation results of high-temperature pressurized water corrosion of RAFM and copper alloys with varied DO conditions.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述タイプ Other
内容記述 The 20th International Conference on Fusion Reactor Materials (ICFRM-20)
発表年月日
日付 2021-10-27
日付タイプ Issued
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