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Long pulse advanced tokamak discharges in the DIII-D tokamak

P.I. Petersen for the DIII-D Team2003年被引用 2Nuclear FusionIF 3出版社

One of the main goals for the DIII-D research programme is to establish an advanced tokamak (AT) plasma with high bootstrap current fraction that can be sustained in-principle steady-state. Substantial progress has been made in several areas during the last year. The resistive wall mode (RWM) stabilization has been done with spinning plasmas in which the plasma pressure has been extended well above the no-wall beta limit. The 3/2 neoclassical tearing mode (NTM) has been stabilized by electron cyclotron heating (ECH) of the magnetic islands, which drives current to substitute the missing bootstrap current. In these experiments either the plasma was moved or the toroidal field was changed to overlap the ECH resonance with the location of the NTMs. Effective disruption mitigation has been obtained by massive noble gas injection into shots where disruptions were deliberately triggered. The massive gas puff causes a fast and clean current quench with essentially all the plasma energy radiated fairly uniformly to the vessel walls. The run-away electrons that are normally seen accompanying disruptions are suppressed by the large density of electrons still bound on the impurity nuclei. Major elements required to establish integrated, long pulse, AT operations have been achieved in DIII-D: βT = 4.2%, βP = 2, fBS = 65%, and βNH89P = 10 for 600 ms (∼4τE). The next challenge is to integrate the different elements, which will be the goal for the next five years when additional control will be available. Twelve RWM coils are scheduled to be installed in DIII-D during the summer of 2003. Future plans include upgrading the tokamak pulse length capability and increasing the ECH power, to control the current profile evolution.

日本語訳

DIII-D研究プログラムの主な目標の一つは、高いブートストラップ電流割合を持ち、原理的に定常状態で維持できる先進トカマク(AT)プラズマを確立することである。昨年、いくつかの領域で substantial な進展があった。抵抗性壁モード(RWM)の安定化は、プラズマ圧力が無壁ベータ限界をはるかに超えて拡張された回転プラズマを用いて達成された。3/2新古典ティアリングモード(NTM)は、磁気島の電子サイクロトロン加熱(ECH)によって安定化された。これは、失われたブートストラップ電流を補う電流を駆動するものである。これらの実験では、ECH共鳴をNTMの位置と重ねるために、プラズマを移動させるか、トロイダル磁場を変更した。効果的なディスラプション緩和は、意図的にディスラプションを引き起こしたショットへの大量の希ガス注入によって得られた。大量ガスパフは、本質的に全てのプラズマエネルギーが容器壁にほぼ均一に放射され、速くて清浄な電流クエンチを引き起こす。通常ディスラプションに伴って見られる逃走電子は、不純物原子核にまだ束縛された電子の高密度によって抑制される。統合された長パルスAT運転を確立するために必要な主要要素は、DIII-Dで達成された:βT = 4.2%、βP = 2、fBS = 65%、およびβNH89P = 10を600 ms(∼4τE)の間。次の課題は、異なる要素を統合することであり、これは追加の制御が利用可能になる今後5年間の目標となる。12個のRWMコイルが2003年の夏にDIII-Dに設置される予定である。将来の計画には、電流分布の時間発展を制御するために、トカマクのパルス長能力の向上とECHパワーの増加が含まれる。

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diii-d高精度(タイトル一致)

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DIII-DAdvanced tokamak
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