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Development of tungsten divertor components for ITER in Japan
https://repo.qst.go.jp/records/74734
https://repo.qst.go.jp/records/7473488f2a538-ee53-421c-89ea-e3eab1a63655
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2019-03-14 | |||||
| タイトル | ||||||
| タイトル | Development of tungsten divertor components for ITER in Japan | |||||
| 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 |
江里, 幸一郎
× 江里, 幸一郎× 鈴木, 哲× 関, 洋治× 平山, 智之× 山田, 弘一× Hirai, T.× Escourbiac, F.× Ezato, Koichiro× Suzuki, Satoshi× Seki, Yoji× Hirayama, Tomoyuki× Yamada, Hirokazu |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W onoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m2 and they met the requirements for W technologies qualification programed by the IO. Upon the successful results, JADA has launched series of qualification programs toward the mass production of components. Furthermore, JADA successfully verified the water flow design inside the OVT is fulfilling the ITER requirements. The flow test was done using a OVT prototype with dummy cooling tubes. | |||||
| 書誌情報 |
Fusion Engineering and Design 巻 136, p. 683-689, 発行日 2018-11 |
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| 出版者 | ||||||
| 出版者 | Elsevier | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 0920-3796 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.fusengdes.2018.03.057 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://www.sciencedirect.com/science/article/pii/S092037961830276X | |||||
