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Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development
https://repo.qst.go.jp/records/2001299
https://repo.qst.go.jp/records/20012994e6063ef-a712-4262-8883-ae492b7de73a
| アイテムタイプ | 学術雑誌論文 / Journal Article(1) | |||||||||
|---|---|---|---|---|---|---|---|---|---|---|
| 公開日 | 2024-08-28 | |||||||||
| タイトル | ||||||||||
| タイトル | Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development | |||||||||
| 言語 | en | |||||||||
| 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 | |||||||||
| 著者 |
Nakajima Motoki
× Nakajima Motoki
× Nozawa Takashi
|
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| 抄録 | ||||||||||
| 内容記述タイプ | Abstract | |||||||||
| 内容記述 | The activated corrosion product assessments of fusion structural materials are essential to designing components and evaluating workers' radiation exposure. This paper first gives the R&D status of the high-temperature pressurized water corrosion study of reduced activation ferritic/martensitic steels and chromium?zirconium?copper (CuCrZr) alloys, which are the leading candidate materials of fusion reactor in-vessel components such as breeding blanket and divertor, which are utilized in high-temperature and high-pressure water, and the recent progress of corrosion test apparatus simulating the unique environment of a fusion reactor will also be presented. | |||||||||
| 書誌情報 |
NUCLEAR FUSION 巻 64, 号 10, 発行日 2024-08 |
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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 | 1741-4326 | |||||||||
| DOI | ||||||||||
| 識別子タイプ | DOI | |||||||||
| 関連識別子 | 10.1088/1741-4326/ad6e04 | |||||||||
