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

Neoclassical heat flux due to poloidal electric field in arbitrary collisionality regime

M Taguchi1993年Plasma Physics and Controlled FusionIF 2.2出版社

A poloidally varying electrostatic potential due to the toroidal drift and heat flux across a flux surface generated by this potential are investigated for a multi-species plasma in tokamaks. By determining this electrostatic potential self-consistently using quasi-neutrality, the heat flux is calculated in the banana, plateau and collisional regimes. Using the results in these asymptotic regimes, a continuously valid expression throughout all collisionality regimes is presented. The electron heat flux is found to exceed the conventional one in the absence of the poloidally varying potential by a factor square root mi/me in all collisionality regimes, where me and mi are the masses of the electron and the ion. The numerical factor for the continuously valid expression is explicitly computed for a simple plasma in a tokamak with circular cross section. An analytic form for the heat flux in a weakly modulated magnetic field is also discussed.

日本語訳

多種イオン種プラズマを対象に、トロイダル方向のドリフトに起因するポロイダル方向に変化する静電ポテンシャルと、それによって生成される磁気面を横切る熱流束をトカマクにおいて調査する。この静電ポテンシャルを準中性条件を用いて自己無撞着に決定することにより、バナナ領域、プラトー領域、衝突領域における熱流束を計算する。これらの漸近領域における結果を用いて、全衝突領域にわたって連続的に有効な熱流束の表式を提示する。電子の熱流束は、ポロイダル方向に変化するポテンシャルが存在しない場合の従来の値と比較して、全衝突領域において√(mi/me)倍(ここでmeおよびmiはそれぞれ電子およびイオンの質量)だけ大きくなることが見出された。円形断面を有するトカマクにおける単純なプラズマに対して、連続的に有効な表式における数値係数を明示的に計算する。さらに、弱く変調された磁場中での熱流束に対する解析的表式についても議論する。

wiki

Collisionality
この論文にはまだAI要約がありません。

関連論文

Theory for neoclassical toroidal plasma viscosity in tokamaks

2012Plasma Physics and Controlled Fusion

Comments on 'Neoclassical heat flux due to poloidal electric field in arbitrary collisionality regime'

1995Plasma Physics and Controlled Fusion

New heat flux model for non-axisymmetric divertor infrared structures

2021Nuclear Fusion

H-factors derived from electron dynamics in tokamaks

1996Plasma Physics and Controlled Fusion

Heat loads on poloidal and toroidal edges of castellated plasma-facing components in COMPASS

2018Nuclear Fusion

Magnetic flux coordinates for analytic high-beta tokamak equilibria with flow

2019Plasma Physics and Controlled Fusion

Kinetic effects on a tokamak pedestal ion flow, ion heat transport and bootstrap current

2013Plasma Physics and Controlled Fusion

Variational calculation of neoclassical ion heat flux and poloidal flow in the banana regime for axisymmetric magnetic geometry

2012Plasma Physics and Controlled Fusion

Convective and viscous fluxes in strongly rotating tokamak plasmas

1990Nuclear Fusion

Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER

2017Nuclear Fusion