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

Three-dimensional Cauchy-condition surface method to identify the shape of the last closed magnetic surface in the Large Helical Device

Masafumi Itagaki, Tadaaki Maeda, Takeshi Ishimaru, Gaku Okubo, Kiyomasa Watanabe, Ryosuke Seki, Yasuhiro Suzuki2011年Plasma Physics and Controlled FusionIF 2.2出版社

Kurihara's Cauchy-condition surface (CCS) method, originally developed for axisymmetric tokamak plasma, has been expanded to reconstruct the 3D magnetic field profile outside the non- axisymmetric plasma in the Large Helical Device (LHD). The boundary integral equations (BIEs) in terms of 3D vector potential for magnetic field sensors, flux loops and points along the CCS are solved simultaneously. In the BIE for a flux loop, the portions related to the fundamental solution are integrated along the loop. The rotational symmetry of the plasma is incorporated into the formulation to reduce the number of unknowns. The reconstructed magnetic field caused only by the plasma current agrees fairly well with the reference solution for the LHD, while good agreement is observed when adding the coil current effect to the magnetic field. The magnetic field line tracing using the reconstructed field indicates the plasma boundary (the outer surface of the stochastic region) precisely and the last closed magnetic surface agrees fairly well with the reference one.

日本語訳

コーシー条件面(CCS)法は、もともと軸対称トカマクプラズマ用に開発されたものであるが、大型ヘリカル装置(LHD)における非軸対称プラズマ外部の3次元磁場分布を再構成するために拡張された。磁場センサ、フラックスループ、およびCCSに沿った点に対する3次元ベクトルポテンシャルに関する境界積分方程式(BIE)を同時に解く。フラックスループに対するBIEでは、基本解に関連する部分をループに沿って積分する。プラズマの回転対称性を定式化に組み込むことで、未知数の数を削減する。プラズマ電流のみによる再構成磁場は、LHDの参照解と良好な一致を示し、コイル電流の効果を加えるとさらに良い一致が得られる。再構成された磁場を用いた磁力線追跡により、プラズマ境界(ストキャスティック領域の外側表面)が正確に特定され、最終閉磁気面は参照解と良好に一致する。

装置

lhd高精度(タイトル一致)

wiki

Helical device
この論文にはまだAI要約がありません。

関連論文

Use of a twisted 3D Cauchy condition surface to reconstruct the last closed magnetic surface in a non-axisymmetric fusion plasma

2012Plasma Physics and Controlled Fusion

3D plasma response to the magnetic field structure in the Large Helical Device

2013Nuclear Fusion

Hydromagnetic equilibria and their proper coordinates

1960Nuclear Fusion

Reconstruction of the plasma surface in a RFP in the presence of non-axisymmetric perturbations

1999Plasma Physics and Controlled Fusion

Equilibrium configurations of reverse field pinch plasma with a helical magnetic axis

1984Nuclear Fusion

A fast, magnetics-free flux surface estimation and q-profile reconstruction algorithm for feedback control of plasma profiles

2013Plasma Physics and Controlled Fusion

Impact of magnetic topology on radial electric field profile in the scrape-off layer of the Large Helical Device

2016Nuclear Fusion

Plasma stabilization by a high-frequency rotational field

1972Nuclear Fusion

Magnetic diagnostics in the large helical device

1997Fusion Engineering and Design

3D numerical simulations of energy transport in the stochastic boundary of TEXTOR-DED with a finite difference method

2008Nuclear Fusion