FusionPapers
図版検索wiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Numerical study on a novel method for the plasma vertical position control using non-axisymmetric coils in JT-60SA

Y Ko, S Inoue, S Kojima, Y Miyata, H Urano, T Suzuki, N Aiba2025年9月Plasma Physics and Controlled FusionIF 2.2出版社

A numerical investigation explored the feasibility of controlling the plasma vertical position using non-axisymmetric coils in JT-60SA. Non-axisymmetric coils offer an alternative to conventional axisymmetric in-vessel coils, addressing challenges in installation and maintenance, particularly in the context of the Japanese DEMO reactor. However, the main concern with using non-axisymmetric coils is the potential generation of locked modes, and the consumption of control margins for other control actions such as edge localized mode suppression. To address such challenges,, we developed control logic to maximize accessible elongation while simultaneously minimizing coil currents. To assess controllability, we employed a magnetohydrodynamic equilibrium control simulator (MECS) and used vacuum magnetic field analysis. We demonstrated that with the application of non-axisymmetric coils, the plasma elongation was extended from 1.75 which was achieved with superconducting poloidal field (SCPF) coils to 1.95, even in the presence of a minor Ip disruption. We also found that an error field correction coil (EFCC) could control during full discharge from ramp-up to ramp-down. The impact of non-axisymmetric magnetic fields on locked modes was evaluated using a three-mode error index (), revealing that n = 1 perturbations remained within acceptable limits () in most scenarios.

日本語訳

数値調査により、JT-60SAにおいて非軸対称コイルを用いたプラズマ鉛直位置制御の実現可能性を検討した。非軸対称コイルは、従来の軸対称真空容器内コイルに代わる選択肢を提供し、特に日本のDEMO炉における設置および保守の課題に対処するものである。しかしながら、非軸対称コイルを使用する際の主な懸念は、ロックモードが発生する可能性と、周辺局在モード抑制などの他の制御動作のための制御マージンを消費することである。このような課題に対処するため、到達可能な伸長度を最大化すると同時にコイル電流を最小化する制御ロジックを開発した。制御可能性を評価するために、磁気流体力学平衡制御シミュレータ(MECS)を採用し、真空磁場解析を用いた。非軸対称コイルの適用により、超伝導ポロイダル磁場(SCPF)コイルで達成された1.75から、軽微なIpディスラプションが存在する場合でも、プラズマ伸長度が1.95まで拡張されることを実証した。また、誤差磁場補正コイル(EFCC)が、ランプアップからランプダウンまでの全放電期間を通じて制御できることも見いだした。非軸対称磁場がロックモードに及ぼす影響は、三モード誤差指標()を用いて評価され、n = 1摂動がほとんどのシナリオで許容限界()以内に留まることが明らかになった。

装置

jt-60sa高精度(タイトル一致)

wiki

JT-60SA

AIによる論文要約

JT-60SAにおける非軸対称コイルを用いたプラズマ垂直位置制御に関する数値的研究
JAこのペーパーは、プラズマ制御技術に興味のある核融合研究者や学生に向けたものです。非軸対称コイルを用いたプラズマ位置制御の可能性と課題について理解を深めることができます。#PlasmaPositionControl #NonaxisymmetricCoils #JT60SA #VerticalPositionControl
LLM向け: {'Title': 'Numerical study on a novel method for the plasma vertical position co…

この研究は、JT-60SAでの非軸対称コイルを使ったプラズマ垂直位置制御の可能性を探っています。従来の軸対称コイルに比べ、非軸対称コイルは設置や保守が容易です。ただし、ロックドモードの発生や、ELM抑制などの他の制御に影響する可能性があります。そこで、ロックドモードを抑えつつ、プラズマ伸長率を最大化する制御手法を開発しました。シミュレーションの結果、非軸対称コイルを使うことで、伸長率を1.75から1.95まで向上できることを示しました。

Numerical study on a novel method for the plasma vertical position control using non-axisymmetric coils in JT-60SA
ENThis paper is of interest to fusion researchers and engineers working on plasma control systems, particularly those involved in the development of the JT-60SA device or other fusion reactors with similar challenges.#PlasmaControl #VerticalPosition #NonAxisymmetricCoils #JT60SA #FusionReactor
LLM向け: {'Title': 'Numerical study on a novel method for the plasma vertical position co…

This paper explores a new way to control the vertical position of plasma in the JT-60SA fusion device using non-axisymmetric coils. This approach offers advantages over traditional coils, but also presents challenges like locked modes. The researchers developed control logic to maximize plasma elongation while minimizing coil currents, and found that non-axisymmetric coils can extend the plasma elongation and provide effective control throughout the discharge.

[Numerical study on a novel method for the plasma vertical position control using non-axisymmetric coils in JT-60SA]
ENThis paper would be of interest to fusion researchers and engineers working on plasma control and reactor design, as it presents a novel solution to a key challenge in fusion device operation.#PlasmaVerticalControl #NonAxisymmetricCoils #FusionReactorDesign
LLM向け: {'Title': 'Numerical study on a novel method for the plasma vertical position co…

This paper explores a new way to control the vertical position of plasma in the JT-60SA fusion device using non-axisymmetric coils, which can address installation and maintenance challenges. The study shows that this method can extend the plasma elongation while minimizing coil currents and controlling disruptions, making it a promising approach for future fusion reactors.

関連論文

Measurement of tokamak error fields using plasma response and its applicability to ITER

2014Nuclear Fusion

Optimizing multi-modal, non-axisymmetric plasma response metrics with additional coil rows on DIII-D

2019Nuclear Fusion

Stellarators and the path from ITER to DEMO

2008Plasma Physics and Controlled Fusion

Feasibility studies on plasma vertical position control by ex-vessel coils in ITER-like tokamak fusion reactors

1993Fusion Engineering and Design

SPARC tokamak error field expectations and physics-based correction coil design

2026Nuclear Fusion

Stabilization of the vertical instability by non-axisymmetric coils

2016Nuclear Fusion

Correcting small magnetic field non-axisymmetries

1994Nuclear Fusion

Modular coils and plasma configurations for quasi-axisymmetric stellarators

2010Nuclear Fusion

3D vacuum magnetic field modelling of the ITER ELM control coil during standard operating scenarios

2013Nuclear Fusion

Multimode observations and 3D magnetic control of the boundary of a tokamak plasma

2013Nuclear Fusion