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

Nonlinear error-field penetration in low density ohmically heated tokamak plasmas

R Fitzpatrick2012年Plasma Physics and Controlled FusionIF 2.2出版社

A theory is developed to predict the error-field penetration threshold in low density, ohmically heated, tokamak plasmas. The novel feature of the theory is that the response of the plasma in the vicinity of the resonant surface to the applied error-field is calculated from nonlinear drift-MHD (magnetohydrodynamical) magnetic island theory, rather than linear layer theory. Error-field penetration, and subsequent locked mode formation, is triggered once the destabilizing effect of the resonant harmonic of the error-field overcomes the stabilizing effect of the ion polarization current (caused by the propagation of the error-field-induced island chain in the local ion fluid frame). The predicted scaling of the error-field penetration threshold with engineering parameters is , where br is the resonant harmonic of the vacuum radial error-field at the resonant surface, BT the toroidal magnetic field-strength, ne the electron number density at the resonant surface and R0 the major radius of the plasma. This scaling—in particular, the linear dependence of the threshold with density—is consistent with experimental observations. When the scaling is used to extrapolate from JET to ITER, the predicted ITER error-field penetration threshold is (br/BT)crit ∼ 5 × 10−5, which just lies within the expected capabilities of the ITER error-field correction system.

日本語訳

低密度オーミック加熱トカマクプラズマにおける誤差磁場浸透の予測理論を構築する。この理論の新規性は、共鳴面近傍のプラズマの誤差磁場に対する応答を、線形層理論ではなく非線形ドリフトMHD(磁気流体力学)磁気島理論から計算することにある。誤差磁場浸透、およびそれに続くロックモードの発生は、誤差磁場の共鳴高調波の不安定化効果が、誤差磁場誘起磁気島列の局所イオン流体中の伝播に起因するイオン分極電流の安定化効果を上回るときに引き起こされる。誤差磁場浸透閾値の工学パラメータに対するスケーリングは、brを共鳴面における真空誤差磁場の共鳴成分、BTをトロイダル磁場強度、neを共鳴面における電子密度、R0をプラズマの主半径とすると、 と予測される。このスケーリング、特に閾値の密度に対する線形依存性は、実験観測と一致する。このスケーリングをJETからITERへ外挿すると、予測されるITERの誤差磁場浸透閾値は(br/BT)crit ∼ 5 × 10⁻⁵となり、これはITER誤差磁場補正システムの想定能力の範囲内にちょうど収まる。

装置

iter中精度(概要文一致)jet中精度(概要文一致)

wiki

Ohmic heating
この論文にはまだAI要約がありません。

関連論文

Error field experiments in JET

2000Nuclear Fusion

Density scaling of error field penetration in radio-frequency-dominant heating plasmas in the EAST tokamak

2021Nuclear Fusion

New insights into error field assessment from mode coupling effects based on RMP spectrum scanning experiments in EAST

2025Nuclear Fusion

Parametric dependencies of locked mode thresholds in KSTAR L-mode plasmas

2021Nuclear Fusion

Observation and correction of non-resonant error fields in NSTX

2010Plasma Physics and Controlled Fusion

Lack of dependence on resonant error field of locked mode island size in ohmic plasmas in DIII-D

2015Nuclear Fusion

Density scaling on n  =  1 error field penetration in ohmically heated discharges in EAST

2018Nuclear Fusion

Progress in understanding error-field physics in NSTX spherical torus plasmas

2010Nuclear Fusion

Error field detection in DIII-D by magnetic steering of locked modes

2014Nuclear Fusion

Error field correction in DIII-D Ohmic plasmas with either handedness

2011Nuclear Fusion