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Extension of the operating space of high-b N fully non-inductive scenarios on TCV using neutral beam injection
https://repo.qst.go.jp/records/77573
https://repo.qst.go.jp/records/7757321a11043-72cb-4f43-b1f2-a461df5ebf2e
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2019-11-21 | |||||
| タイトル | ||||||
| タイトル | Extension of the operating space of high-b N fully non-inductive scenarios on TCV using neutral beam injection | |||||
| 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 |
Piron, C.
× Piron, C.× Garcia, J.× Agostini, M.× Fontana, M.× Giruzzi, G.× Gobbin, M.× Goodman, T.P.× Karpushov, A.N.× Kong, M.× Merle, A.× J. Morales× Nowak, S.× Pigatto, L.× Sauter, O.× Testa, D.× Vallar, M.× Yoshida, Maiko× TCV Team and The EUROfusion MST1 Team, The× Maiko, Yoshida |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The fully non-inductive sustainment of high normalized beta plasmas (βN) is a crucial challenge for the steady-state operation of a tokamak reactor. In order to assess the difficulties facing such scenarios, steady-state regimes have been explored on the tokamak à configuration variable (TCV) using the newly available 1 MW neutral beam injection (NBI) system. The operating space is extended towards plasmas that are closer to those expected in JT-60SA and ITER, i.e. with significant NBI and electron cyclotron resonance heating and current drive (ECRH/CD), bootstrap current and fast ion (FI) fraction. βN values up to 1.4 and 1.7 are obtained in lower single null L-mode (H98(y, 2) ∼ 0.8) and H-mode (H98(y, 2) ∼ 1) plasmas, respectively, at zero time averaged loop voltage and q95 ∼ 6. Fully non-inductive operation is not achieved with NBI alone, whose injection can even increase the loop voltage in the presence of EC waves. A strong contribution to the total plasma pressure of thermal and FIs from NBI is experimentally evidenced and confirmed by interpretative ASTRA and NUBEAM modeling, which further predicts that FI charge-exchange reactions are the main loss channel for NBH/CD efficiency. Internal transport barriers, which are expected to maximize the bootstrap current fraction, are not formed in either the electron or the ion channel in the plasmas explored to date, despite a significant increase in the toroidal rotation and FI fraction with NBI, which are known to reduce turbulence. First results on scenario development of high-βN fully non-inductive H-mode plasmas are also presented. | |||||
| 書誌情報 |
Nuclear Fusion 巻 59, 号 11, p. 096012, 発行日 2019-09 |
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| 出版者 | ||||||
| 出版者 | IOP Science | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 0029-5515 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1088/1741-4326/ab2bb6 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://iopscience.iop.org/article/10.1088/1741-4326/ab2bb6 | |||||
