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

Physics and optimization of plasma startup in the RFP

W. Mao, B.E. Chapman, W.X. Ding, L. Lin, A.F. Almagri, J.K. Anderson, D.J. Den Hartog, J. Duff, J. Ko, S.T.A. Kumar2015年被引用 3Nuclear FusionIF 3出版社

In the tokamak and reversed-field pinch (RFP), inductively driven toroidal plasma current provides the confining poloidal magnetic field and ohmic heating power, but the magnitude and/or duration of this current is limited by the available flux swing in the poloidal field transformer. A portion of this flux is consumed during startup as the current is initiated and ramped to its final target value, and considerable effort has been devoted to understanding startup and minimizing the amount of flux consumed. Flux consumption can be reduced during startup in the RFP by increasing the toroidal magnetic field, Bti, applied to initiate the discharge, but the underlying physics is not yet entirely understood. Toward increasing this understanding, we have for the first time in the RFP employed advanced, non-invasive diagnostics on the Madison Symmetric Torus to measure the evolution of current, magnetic field, and kinetic profiles during startup. Flux consumption during startup is dominantly inductive, but we find that the inductive flux consumption drops as Bti increases. The resistive consumption of flux, while relatively small, apparently increases with Bti due to a smaller electron temperature. However, the ion temperature increases with Bti, exceeding the electron temperature and thus reflecting non-collisional heating. Magnetic fluctuations also increase with Bti, corresponding primarily to low-n modes that emerge sequentially as the safety factor profile evolves from tokamak-like to that of the RFP.

日本語訳

トカマクおよび反転磁場配位(RFP)において、誘導駆動されるトロイダルプラズマ電流は閉じ込め用ポロイダル磁場とオーミック加熱電力を提供するが、この電流の大きさおよび/または持続時間は、ポロイダル磁場変圧器における利用可能な磁束掃引によって制限される。この磁束の一部は、電流が立ち上げられ最終目標値まで上昇する際のスタートアップ中に消費され、スタートアップの理解と消費磁束の低減にかなりの努力が払われてきた。RFPにおけるスタートアップ中の磁束消費は、放電開始時に印加されるトロイダル磁場Btiを増加させることで低減できるが、その基礎となる物理は完全には理解されていない。この理解を深めるために、我々はマディソン・シンメトリック・トーラスにおいて、スタートアップ中の電流、磁場、運動論的プロファイルの時間発展を測定する先進的な非侵襲診断法を初めて採用した。スタートアップ中の磁束消費は主に誘導的であるが、誘導磁束消費はBtiの増加に伴って減少することがわかった。一方、抵抗性磁束消費は比較的小さいものの、電子温度の低下によりBtiの増加に伴って増加するようである。しかし、イオン温度はBtiとともに上昇し、電子温度を超えることから、非衝突加熱の存在が示唆される。また、磁気揺動もBtiとともに増加し、これは安全係数プロファイルがトカマク様からRFP様へと進化するにつれて順次現れる主に低次のモードに対応している。

wiki

Reversed field pinchPlasma start-up
この論文にはまだAI要約がありません。

関連論文

Measurement of magnetic fluctuation-induced heat transport in tokamaks and RFP

1996Plasma Physics and Controlled Fusion

Startup of reversed field pinches and current ramping using dynamo action

1988Nuclear Fusion

Reduction of poloidal magnetic flux consumption during plasma current ramp-up in DEMO relevant plasma regimes

2017Nuclear Fusion

Tokamak startup using outboard current injection on the Pegasus Toroidal Experiment

2011Nuclear Fusion

Tokamak-like confinement at a high beta and low toroidal field in the MST reversed field pinch

2003Nuclear Fusion

Experimental demonstration of RF-induced particle flux reduction using a toroidally localized electrode in a divertor-leg-like plasma

2026Plasma Physics and Controlled Fusion

Using a multipole expansion for startup in the DIII-D tokamak

1998Nuclear Fusion

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

1993Plasma Physics and Controlled Fusion

Inductive plasma current start-up by the outer vertical field coil in a spherical tokamak

1999Plasma Physics and Controlled Fusion

Rotation dependent ion fluxes in front of resonant magnetic perturbation coils

2013Nuclear Fusion