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Heating neutral beams for ITER: Present status
https://repo.qst.go.jp/records/48256
https://repo.qst.go.jp/records/482565b45d762-70db-44d7-a6ea-d9d8a5654e52
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-07-31 | |||||
| タイトル | ||||||
| タイトル | Heating neutral beams for ITER: Present status | |||||
| 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 |
Singh, M.J.
× Singh, M.J.× Boilson, D.× Hemsworth, R.× Chareyre, J.× Decamps, H.× Delmas, E.× Geli, F.× Graceffa, J.× Schunke, B× Svensson, L.× Shah, D.× El, Ouazzani A.× Urbani, M.× De, Esch H.P.L.× Antoni, V.× Chitarin, G.× Serianni, G.× Marcuzzi, D.× Toigo, V.× Zaccaria, P.× Fantz, U.× Franzen, P.× Heinemann, B.× Kraus, W.× Kashiwagi, M.× Hanada, M.× Tobari, H.× Kuriyama, M.× Masiello, A.× Bonicelli, T.× 柏木 美恵子× 花田 磨砂也× 戸張 博之 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The heating neutral beam (HNB) systems at ITER are designed to inject a total of 33 MW of either 1 MeV D0 or 870 keV H0 beams into the ITER plasma using two injectors with a possible addition of a third injector later to increase the injected power to ~50 MW. The injectors become radioactive due to the neutron flux from ITER and, in order to avoid the resulting complex remote maintenance, the design, choice of materials and the manufacturing process of each component of the injector is, wherever possible, such that they survive the life time of ITER. To ensure a smooth operational phase of neutral beams at ITER a neutral beam test facility (NBTF) is under construction at Consorzio RFX, Padova, (hereinafter referred to as RFX), which consists of 2 test beds, the 100 kV “SPIDER”, and a 1 MV “MITICA” facilities, which will be used to optimize the source operation for H and D beams. MITICA is essentially a full scale ITER prototype injector for the ITER beam parameters. The manufacturing and operation of the facility will allow validation of the operational space of the injectors and provide valuable information about the manufacturing processes applicable to HNB components. Operation of the two facilities is expected to begin in 2016 and 2019 respectively. Currently experiments on the ELISE facility with a half ITER sized RF beam source are underway. ITER relevant parameters for the H beams have almost been achieved. Efforts are underway to optimise the same with D beams. The experimental database from ELISE will be an important input for establishing the ITER relevant parameter space on the SPIDER source. This paper discusses the present status of the design and development of the injectors for ITER and the progress on the test facilities. | |||||
| 書誌情報 |
IEEE Transaction plasma science 巻 44, 号 9, p. 1496-1505, 発行日 2016-09 |
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| 出版者 | ||||||
| 出版者 | IEEE | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 2155-9953 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1109/TPS.2016.2586598 | |||||
