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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/83953cc87b9c5-b9ff-4e94-b351-9273d8963136
Item type | 会議発表用資料 / Presentation(1) | |||||
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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× Huang, Yenjui× Takashi, Nozawa× Motoki, Nakajima× Huang, Yenjui× 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 |