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Optimization of high beta steady-state scenarios at TCV in support of JT-60SA
https://repo.qst.go.jp/records/72836
https://repo.qst.go.jp/records/728363b835f35-6c93-4dcc-8680-3ed41bcb1eb6
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-06-29 | |||||
| タイトル | ||||||
| タイトル | Optimization of high beta steady-state scenarios at TCV in support of JT-60SA | |||||
| 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_c94f | |||||
| 資源タイプ | conference object | |||||
| 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 |
Garcia, J.
× Garcia, J.× Piron, C.× Goodman, T.× Agostini, M.× Fontana, M.× Giruzzi, G.× Gobbin, M.× Karpushov, A.× Kong, M.× Merle, A.× Morales, J.× Nowak, S.× Pigatto, L.× Sauter, O.× Testa, D.× M.Vallar× 吉田, 麻衣子× 吉田 麻衣子 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The mission of the future tokamak device JT-60SA, currently under construction at Naka, is to produce steady-state scenarios at high beta and density in support of the ITER and DEMO steady-state program. The development of such fully non-inductive plasmas both at high normalized (βN) and poloidal (βp) beta is a crucial challenge for the steady-state operation of a tokamak reactor due to a significant number of exigent physics requirements. One of the key elements that can alleviate such difficulties is performing previous validated modelling with the aim of preparing the target scenarios and find possible solutions. However, validated models in conditions relevant for JT-60SA or the future reactor, i.e. with significant NBI and ECRH current drive, bootstrap current and fast ion fraction for several current diffusion times, is difficult due to the limited number of such plasmas available. In order to assess the difficulties found on those scenarios, steady-state regimes have been explored at TCV using the newly available 1MW Neutral Beam Injection (NBI) system [1]. Compared to the past, when fully non-inductive plasmas were sustained using Electron Cylotron (EC) waves only [2,3], the operating space has been now extended towards plasma conditions compatible with co-Ip NBI heating, i.e. plasma current (Ip=[130, 150]kA) and density (ne,0≈[2,3]e19m-3) with a combination of on-axis and off-axis heating schemes. βN values up to 1.4 and 1.7 have been reached in fully non-inductive plasmas (Vloop~0) in L-mode and H-mode respectively, both occurring with central EC and NB deposition and H/CD in the co-Ip direction. For comparison, note that βN<0.4 and Vloop>0.7V are typically obtained in similar Ohmic plasmas. Fully non-inductive operation could not be achieved with NBI alone (Vloop>0.5V). Adding NBI results in an increase or decrease of Vloop depending on other plasma parameters. For instance, NBI can significantly increase the density which in turn reduces the ECCD efficiency. One of the routes explored has been the creation of Internal Transport Barriers (ITB) in order to maximize the bootstrap current fraction. This turned out to be a challenge as they were not formed in either the electron or the ion channel in the plasmas explored up to date in spite of the fact of a significant increasing of the toroidal rotation and fast ion (FI) fraction with NBI, which are known to reduce turbulence [4]. The possibility that these plasmas are Trapped Electron Mode (TEM) turbulence dominated, which is less susceptible to such stabilizations [5], is being analysed in dedicated turbulence analyses. Additionally, excessive on-axis NBI current obtained prevented the onset of strong ITB’s as previously shown in modelling [6]. |
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| 会議概要（会議名, 開催地, 会期, 主催者等） | ||||||
| 内容記述タイプ | Other | |||||
| 内容記述 | 2nd Asia-Pacific Conference on Plasma Physics | |||||
| 発表年月日 | ||||||
| 日付 | 2018-11-12 | |||||
| 日付タイプ | Issued | |||||
