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

Resistivity scaling of rotating magnetic field current drive in FRCs

A.L. Hoffman, H.Y. Guo, R.D. Milroy, Z.A. Pietrzyk2003年被引用 22Nuclear FusionIF 3出版社

Rotating magnetic fields (RMFs) have been used to both form and sustain low density, prolate FRCs in the translation confinement and sustainment (TCS) facility. The two most important factors governing performance are the plasma resistivity, which sets the maximum density for which toroidal current can be maintained, and the energy loss rate, which sets the plasma temperature. The plasma resistivity has been determined by carefully measuring the amount of RMF power absorbed by the FRC. When the ratio of RMF magnitude, Bω, to external poloidal confinement field, Be, is high, this resistivity is very adversely affected by the RMF drive process. However, when Bω/Be falls below about 0.3, the resistivity returns to values typical of non-driven FRCs. The observed scaling leads to a density dependence of ne ∼ Bω/rsω1/2 where rs is the FRC separatrix radius and ω is the RMF frequency. Since the FRC contains little or no toroidal field, Be is proportional to (neTt)1/2 where Tt = Te + Ti is the sum of the electron and ion temperatures. In the present experiments, except for the initial start-up phase where Tt can exceed 100 eV, the plasma temperature is limited to about 40 eV by high oxygen impurity levels. Thus, low Bω/Be, low resistivity operation was only realized by operating at low values of Bω. The RMF drive sustains particles as well as flux, and resistive input powers can be in the MW range at higher values of Bω, so that high temperature, steady-state operation should be possible once impurity levels are reduced. Changes are being made to the present 'O-ring' sealed, quartz chambered TCS to provide bakable metal walls and wall conditioning as in other quasi-steady fusion facilities.

日本語訳

回転磁場(RMF)は、並進閉じ込め・持続(TCS)装置において、低密度・長尺の場反転配位(FRC)を形成し、維持するために使用されてきた。性能を左右する最も重要な2つの因子は、プラズマ抵抗率(トロイダル電流を維持できる最大密度を決定する)とエネルギー損失率(プラズマ温度を決定する)である。プラズマ抵抗率は、FRCによって吸収されるRMFパワーを精密に測定することによって決定された。RMFの大きさBωと外部ポロイダル閉じ込め磁場Beの比が高い場合、この抵抗率はRMF駆動プロセスによって著しく悪影響を受ける。しかし、Bω/Beが約0.3未満に低下すると、抵抗率は非駆動FRCに典型的な値に戻る。観測されたスケーリングは、密度依存性ne ∼ Bω/rsω1/2をもたらす。ここで、rsはFRCセパラトリックス半径、ωはRMF周波数である。FRCはほとんどまたは全くトロイダル磁場を含まないため、Beは(neTt)1/2に比例し、ここでTt = Te + Tiは電子温度とイオン温度の合計である。現在の実験では、初期立ち上げ段階(Ttが100 eVを超え得る)を除いて、プラズマ温度は高い酸素不純物レベルによって約40 eVに制限されている。したがって、低いBω/Be、すなわち低抵抗率の運転は、低いBωの値でのみ実現された。RMF駆動は粒子と磁束の両方を維持し、より高いBωの値では抵抗性入力パワーがMW範囲に達し得るため、不純物レベルが低減されれば、高温・定常運転が可能になるはずである。他の準定常核融合装置と同様に、現在の石英チャンバーをベーク可能な金属壁チャンバーに交換し、壁コンディショニングを施すための変更が進行中である。

wiki

Current drive
この論文にはまだAI要約がありません。

関連論文

Long pulse FRC sustainment with enhanced edge driven rotating magnetic field current drive

2005Nuclear Fusion

Sustainment and additional heating of high-beta field-reversed configuration plasmas

2005Nuclear Fusion

Comparison of rotamak plasmas in FRC and ST configurations

2005Plasma Physics and Controlled Fusion

Azimuthally non-uniform equilibrium of field-reversed configuration sustained by rotating magnetic field with spatial high-harmonic components

2009Nuclear Fusion

Energy balance in the CSSU device

1993Nuclear Fusion

Plasma-circuit interactions in rotating magnetic field current drive

2008Plasma Physics and Controlled Fusion

Overview of physics results from the conclusive operation of the National Spherical Torus Experiment

2013Nuclear Fusion

Localized electromagnetic modes in MHD stable regime of the TJ-II Heliac

2006Plasma Physics and Controlled Fusion

Overview of C-2W: high temperature, steady-state beam-driven field-reversed configuration plasmas

2021Nuclear Fusion

Sustainment of FRC-equilibrium by use of a centre solenoid in TS-4

2007Nuclear Fusion