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Resistive wall mode physics and control challenges in JT-60SA high βN scenarios
https://repo.qst.go.jp/records/77688
https://repo.qst.go.jp/records/77688ca782ae2-c52d-4bd7-b36a-996cbba411cf
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2019-11-28 | |||||
タイトル | ||||||
タイトル | Resistive wall mode physics and control challenges in JT-60SA high βN scenarios | |||||
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 |
Pigatto, L.
× Pigatto, L.× Aiba, Nobuyuki× Bolzonella, T.× Hayashi, Nobuhiko× Honda, Mitsuru× Y.Q. Liu× Marchiori, G.× Mastrostefano, S.× Matsunaga, Go× Takechi, Manabu× Villone, F.× Nobuyuki, Aiba× Nobuhiko, Hayashi× Mitsuru, Honda× Go, Matsunaga× Manabu, Takechi |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The superconducting tokamak JT-60SA is being built in Naka (Japan) under the Broader Approach Satellite Tokamak Programme jointly by Europe and Japan, and under the Japanese national programme. JT-60SA has an important supporting mission for the development of fusion energy. It will help in both the exploitation of ITER and in the definition of an optimized DEMO design. The focus of this work is set on high scenarios, in which kink-like instabilities (e.g. one or more resistive wall modes) are potentially unstable and possibly lead to disruptions. As a fundamental step to ensure the safe realization of high plasmas, modeling activities are being carried out for MHD stability and control. The drift-kinetic damping model in particular will be considered in the present work, with a stability study in Scenario 5-like plasmas carried out with MARS-F/K. Resistive wall mode (RWM) stability is found with this model for low plasma rotation and precession drift resonance with thermal ions. The dependence on normalized and flow profile is discussed. The challenge of active control is also addressed, taking advantage of the set of RWM control coils that JT-60SA will install. A dynamic simulator, based on the CarMa code, has been developed for feedback control modeling. A demonstration of this tool is given for one of the aforementioned plasmas. Stabilization of the most unstable RWM is achieved within basic power limits. Potential applications, results and latest development of this tool are discussed. | |||||
書誌情報 |
Nuclear Fusion 巻 59, p. 106028, 発行日 2019-08 |
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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/ab34c0 | |||||
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識別子タイプ | URI | |||||
関連識別子 | https://iopscience.iop.org/article/10.1088/1741-4326/ab34c0/meta |