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Plasma Scenario Modeling for JA DEMO

https://repo.qst.go.jp/records/79362
https://repo.qst.go.jp/records/79362
372ebe09-78ab-49d5-9bc9-078c745231f8
Item type 会議発表用資料 / Presentation(1)
公開日 2020-03-12
タイトル
タイトル Plasma Scenario Modeling for JA DEMO
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 Sakamoto, Yoshiteru

× Sakamoto, Yoshiteru

WEKO 851364

Sakamoto, Yoshiteru

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Hayashi, Nobuhiko

× Hayashi, Nobuhiko

WEKO 851365

Hayashi, Nobuhiko

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Aiba, Nobuyuki

× Aiba, Nobuyuki

WEKO 851366

Aiba, Nobuyuki

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Uto, Hiroyasu

× Uto, Hiroyasu

WEKO 851367

Uto, Hiroyasu

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Special Design Team for Fusion DEMO, Joint

× Special Design Team for Fusion DEMO, Joint

WEKO 851368

Special Design Team for Fusion DEMO, Joint

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Sakamoto, Yoshiteru

× Sakamoto, Yoshiteru

WEKO 851369

en Sakamoto, Yoshiteru

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Hayashi, Nobuhiko

× Hayashi, Nobuhiko

WEKO 851370

en Hayashi, Nobuhiko

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Aiba, Nobuyuki

× Aiba, Nobuyuki

WEKO 851371

en Aiba, Nobuyuki

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Uto, Hiroyasu

× Uto, Hiroyasu

WEKO 851372

en Uto, Hiroyasu

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抄録
内容記述タイプ Abstract
内容記述 In order to proceed the integrated plasma scenario modeling of JA DEMO, (i) core transport simulation, (ii) vertical stability and (iii) MHD stability analyses have been performed. In addition, applicability of no/small ELM regimes to JA DEMO has also been investigated.
On the 1.5-D time-dependent core transport simulation by integrated code TOPICS, the steady-state operation condition with HH = 1.41, betaN = 3.6, fBS = 0.69 is demonstrated by optimizing the heating scenario, where CDBM transport model is used. It is also demonstrated that off-axis ECCD has important roles for maintaining the internal transport barriers (ITBs) for steady-state condition and for controlling the fusion power by control of ITB location. On the vertical stability analysis, the ramp-up scenario of high elongated plasma has been developed by using the plasma equilibrium simulator MECS with 3D eddy current effects. The temporal evolutions of the poloidal beta and internal inductance are evaluated using TOPICS. The result indicates that plasma elongation at 95% of poloidal flux of 1.75 is achievable in JA DEMO. Regarding the MHD stability analysis, the beta limit of JA DEMO plasma has been evaluated by using the linear ideal MHD stability code MARG2D. The beta limit without conducting wall is betaN ~ 2.6, while that with conducting wall can be improved to ~3.5 at the wall radius of rW/a = 1.35. Further improvements are observed with decreasing the wall radius, for example betaN ~ 3.9 at rW/a = 1.30.
It is important to investigate the applicability of no/small ELM regimes to a DEMO. The candidates of the no/small ELM regimes realized in the low collisionality region are grassy ELMy H mode and QH mode, which are observed in many tokamak experiments. The grassy ELM regime can be reduced the ELM energy to ~1% of the pedestal energy. The necessary conditions are the high poloidal beta ~1.4, the high safety factor q95>4, the high triangularity >0.4 and the low elongation <1.45. The DEMO main parameters, that satisfy the necessary conditions of grassy ELMy H mode, will be discussed.
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 6th IAEA DEMO Programme Workshop
発表年月日
日付 2019-10-02
日付タイプ Issued
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