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Progress of Qualification Testing for Full-Scale Plasma-Facing Unit Prototype of Full Tungsten ITER Divertor in Japan
https://repo.qst.go.jp/records/54748
https://repo.qst.go.jp/records/54748c69124c8-50f2-402a-b9c3-5b014922f4da
| Item type | 会議発表論文 / Conference Paper(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-03-31 | |||||
| タイトル | ||||||
| タイトル | Progress of Qualification Testing for Full-Scale Plasma-Facing Unit Prototype of Full Tungsten ITER Divertor in Japan | |||||
| 言語 | ||||||
| 言語 | jpn | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_5794 | |||||
| 資源タイプ | conference paper | |||||
| 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 |
関, 洋治
× 関, 洋治× 江里, 幸一郎× 鈴木, 哲× 横山, 堅二× 山田, 弘一× 平山, 智之× 平井, 武志× Escourbiac, F.× Volodin, A.× Kuznetsov, V.× 関 洋治× 江里 幸一郎× 鈴木 哲× 横山 堅二× 山田 弘一× 平山 智之 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | National Institutes for Quantum and Radiological Science and Technology (QST) reports progress of research and development of a full-tungsten (W) Divertor Outer Vertical Target (OVT) for ITER. Under a framework of a W divertor qualification program, QST manufactured 7 full-scale plasma-facing units (PFUs) as prototypes. Through the manufacturing, (i) all joint surfaces in four PFUs with a casted Cu interlayer successfully passed the ultrasonic testing (UT) and (ii) the profile tolerance of surface in target part of PFUs stayed within ± 0.25 mm. (iii) Moreover QST succeeded in demonstrating a durability for high heat flux (HHF) testing of the repetitive heat load of 10 MW/m2 × 5000 cycles and 20 MW/m2 × 1000 cycles in close collaboration with the ITER organization (IO-CT) and the Russian Domestic Agency (RFDA). These results demonstrated the capability of Japanese industry to produce the PFU of full-W ITER divertor to meet the technical requirements. | |||||
| 書誌情報 |
Proceedings of 26th IAEA Fusion Energy Conference 巻 FIP/2-1Ra, p. 1-6, 発行日 2016-10 |
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