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Characterization of plasma current quench during disruption in EAST tokamak

机译:EAST托卡马克破裂过程中等离子体电流淬灭的表征

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Preliminary analysis of plasma current quench is presented in this paper based on the disruption database. It demon-strates that 26.8%discharges have disrupted in the last 2012 campaign, in addition, plasma disruptive rate grows with the increase of plasma current. Best-fit linear and instantaneous plasma current quench rate is extracted from the recent EAST disruptions, showing that 80%–30%interval of the maximum plasma current is well fit for EAST device. The lowest area-normalized current quench time is 3.33 ms/m2 with the estimated plasma electron temperature being 7.3 eV∼9.5 eV. In the disruption case the maximum eddy current goes up to 400 kA, and a fraction of currents are respectively driven on upper and lower outer plate with nearly 100 MPa–200 MPa stress in the leg.
机译:本文基于干扰数据库对等离子体电流猝灭进行了初步分析。它表明,在上一次2012年的竞选活动中,有26.8%的放电中断,此外,随着等离子体电流的增加,等离子体的破坏率也随之增加。从最近的EAST中断中提取了最佳拟合的线性和瞬时等离子体电流猝灭速率,这表明最大等离子体电流间隔的80%–30%非常适合EAST设备。最小面积归一化电流猝灭时间为3.33 ms / m2,估计的等离子体电子温度为7.3 eV〜9.5 eV。在破裂的情况下,最大涡流达到400 kA,一部分电流分别在上外板和下外板上以大约100 MPa–200 MPa的应力被驱动。

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