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On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress
https://repo.qst.go.jp/records/84639
https://repo.qst.go.jp/records/84639999b0b64-17bb-4993-946d-6b75dee25862
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2021-09-30 | |||||
| タイトル | ||||||
| タイトル | On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress | |||||
| 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 |
Toigo, V.
× Toigo, V.× Marcuzzi, D.× Serianni, G.× Boldrin, M.× Chitarin, G.× Dal Bello, S.× Grando, L.× Luchetta, A.× Pasqualotto, R.× Zaccaria, P.× Mieko, Kashiwagi× Hiroyuki, Tobari× Kazuhiro, Watanabe× Tetsuya, Maejima× Atsushi, Kojima× Eiji, Ooshita× Yasuo, Yamashita× Shunsuke, Konno× Others× Mieko, Kashiwagi× Hiroyuki, Tobari× Kazuhiro, Watanabe× Tetsuya, Maejima× Atsushi, Kojima× Eiji, Ooshita× Yasuo, Yamashita× Shunsuke, Konno |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | To reach fusion conditions and control the plasma configuration in ITER, the next step in tokamak fusion research, two neutral beam injectors (NBIs) will supply 16.5 MW each, by neutralizing accelerated negative hydrogen or deuterium ions. The requirements of ITER NBIs (40A/1 MeV D- ions for ≤1 h, 46A/870 keV H- ions for ≤1000 s) have never been simultaneously attained. So in the Neutral Beam Test Facility (NBTF, Consorzio RFX, Italy) the operation of the full-scale ITER NBI prototype (MITICA) will be tested and optimised up to full performances, focussing on accelerator (including voltage holding), beam optics, neutralisation, residual ion removal. The NBTF includes also the full-scale prototype of the ITER NBI source with 100 keV particle energy (SPIDER), for early investigation of: negative ion production and extraction, source uniformity, negative ion current density and beam optics. This paper will describe the main results of the first two years of SPIDER operation, devoted to characterizing plasma and beam parameters, including investigation of RF-plasma coupling efficiency and magnetic filter field effectiveness in reducing co-extracted electrons. SPIDER is progressing towards the first caesium injection, which aims at increasing the negative ion density. A major shutdown, planned for 2021, to solve the issues identified during the operation and to carry out programmed modifications, will be outlined. The installation of each MITICA power supply and auxiliary system is completed; in-vessel mechanical components are under procurement by Fusion for Energy (F4E). Integration, commissioning and test of the power supplies, procured by F4E and QST, as the Japanese Domestic Agency (JADA), will be presented. In particular, 1.0MV insulating tests were carried out step-by-step and successfully completed. In 2020 integrated tests of the power supplies on the accelerator dummy load started, including the assessment of their resilience to accelerator grid breakdowns using a short-circuit device located in vacuum. The aggressive programme, to validate the NBI design at NBTF and to meet ITER schedule (requiring NBIs in operation in 2032), will be outlined. Unfortunately, in 2020 the coronavirus disease infection affected the NBTF activities. A solution to proceed with integrated power tests despite the coronavirus is presented. |
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| 書誌情報 |
Fusion Engineering and Design 巻 168, p. 112622, 発行日 2021-07 |
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| 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.2021.112622 | |||||
| 関連サイト | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | https://doi.org/10.1016/j.fusengdes.2021.112622 | |||||
