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

Toroidal equilibrium and radial profiles from magnetic measurements in Extrap T1

P Brunsell, Jin Li, E Tennfors1991年Plasma Physics and Controlled FusionIF 2.2出版社

The toroidal equilibrium position in the Extrap T1 toroidal Z-pinch is studied by measuring the currents induced in the external octupole field rings. Radial profiles are obtained by an internal magnetic coil array. From the magnetic field, profiles of current density, plasma pressure, safety factor, resistivity and input power density are deduced. A polynomial model is developed to simulate the measured profiles. The classical ion heat conduction losses in Extrap discharges are calculated using this model and compared to the power input. For polynomials matched to magnetic field profiles measured in experiments, these losses are small. By varying the coefficients of the polynomials, a region is found where the power input can balance the classical heat conduction losses at higher values of Theta and beta 0.

日本語訳

Extrap T1トロイダルZピンチにおけるトロイダル平衡位置は、外部八極磁場リングに誘起される電流を測定することによって研究された。動径プロファイルは、内部磁気プローブアレイによって得られた。磁場から、電流密度、プラズマ圧力、安全係数、抵抗率、および入力電力密度のプロファイルが導出された。測定されたプロファイルをシミュレートするために、多項式モデルが開発された。Extrap放電における古典的なイオン熱伝導損失は、このモデルを用いて計算され、入力電力と比較された。実験で測定された磁場に一致する多項式に対して、これらの損失は小さい。多項式の係数を変化させることにより、より高いシータ値およびベータ0値において、入力電力が古典的な熱伝導損失と釣り合うことができる領域が見出された。

この論文にはまだAI要約がありません。

関連論文

Is it possible to extract information on the plasma pressure profile from magnetic measurements in stellarators?

1994Nuclear Fusion

Experimental plasma equilibrium reconstruction from kinetic and magnetic measurements in the FTU tokamak

1995Nuclear Fusion

Pre-ionization and pre-heat conditions for a compact toroidal plasma experiment in the millitorr pressure range

1973Nuclear Fusion

Energetically resolved multiple-fluid equilibria of tokamak plasmas

2009Plasma Physics and Controlled Fusion

Low-aspect-ratio reversed field pinch plasma equilibria with finite surface toroidal current density

2005Plasma Physics and Controlled Fusion

The effect of net toroidal current on the measurement of diamagnetic beta value in heliotron plasma

2006Plasma Physics and Controlled Fusion

Internal magnetic field structure and parallel electric field profile evolution during the sawtooth cycle in MST

2008Plasma Physics and Controlled Fusion

A global analysis of the behaviour of the ZT-40M reversed field pinch

1995Nuclear Fusion

Mean magnetic field profiles and their dynamics in reversed field pinches

1989Nuclear Fusion

Comparisons of predicted plasma performance in ITER H-mode plasmas with various mixes of external heating

2009Nuclear Fusion