在靠近 W7-X 等离子体边缘的内部岛屿配置中的电子传输障碍和高约束性

IF 3.5 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Nuclear Fusion Pub Date : 2024-09-03 DOI:10.1088/1741-4326/ad703e
N. Chaudhary, M. Hirsch, T. Andreeva, J. Geiger, R.C. Wolf, G.A. Wurden, the W7-X Teama
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To investigate the configuration effects on the plasma confinement, a configuration scan was performed by changing the coil currents to vary the rotational transform between values <inline-formula>\n<tex-math><?CDATA $5/4$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:mn>5</mml:mn><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:mn>4</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn1.gif\"></inline-graphic></inline-formula> and <inline-formula>\n<tex-math><?CDATA $5/6$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:mn>5</mml:mn><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:mn>6</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn2.gif\"></inline-graphic></inline-formula> at the plasma boundary with different power levels (2, 4, 6 MW) of electron cyclotron resonance heating (ECRH) at a maximum plasma density of <inline-formula>\n<tex-math><?CDATA $8 \\times 10^{19}\\,\\textrm{m}^{-2}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:mn>8</mml:mn><mml:mo>×</mml:mo><mml:msup><mml:mn>10</mml:mn><mml:mrow><mml:mn>19</mml:mn></mml:mrow></mml:msup><mml:mstyle scriptlevel=\"0\"></mml:mstyle><mml:msup><mml:mtext>m</mml:mtext><mml:mrow><mml:mo>−</mml:mo><mml:mn>2</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn3.gif\"></inline-graphic></inline-formula>. neutral beam injection (NBI) heating was also applied during some configurations of the scan to create a density ramp and access high densities beyond the X2 ECRH cutoff. For the magnetic configurations, where the <inline-formula>\n<tex-math><?CDATA $5/5$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:mn>5</mml:mn><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:mn>5</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn4.gif\"></inline-graphic></inline-formula> and <inline-formula>\n<tex-math><?CDATA $5/6$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:mn>5</mml:mn><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:mn>6</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn5.gif\"></inline-graphic></inline-formula> island chains were moved closer to separatrix but remaining inside the last closed flux surface, the electron cyclotron emission shows that an electron temperature, <inline-formula>\n<tex-math><?CDATA $T_{\\mathrm e}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>T</mml:mi><mml:mrow><mml:mrow><mml:mi mathvariant=\"normal\">e</mml:mi></mml:mrow></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn6.gif\"></inline-graphic></inline-formula>, pedestal develops already during ECRH heated plasma buildup phase indicating a transport barrier, and the barrier sustains irrespective of changed plasma heating conditions such as NBI in the later part of discharge. The transport barrier is broken by subsequent fast crashes, observed with multiple plasma diagnostics with characteristics such as tokamak edge localized modes, and the corresponding crash amplitude and frequency vary with plasma pressure. The impact of the transport barrier on plasma confinement can be seen through the increased core <inline-formula>\n<tex-math><?CDATA $T_{\\mathrm e}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>T</mml:mi><mml:mrow><mml:mrow><mml:mi mathvariant=\"normal\">e</mml:mi></mml:mrow></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad703eieqn7.gif\"></inline-graphic></inline-formula> profile, which could be responsible for the overall increase in the stored diamagnetic energy by approximately 10% for these configurations. After the plasma heating is terminated, a backwards transition to a degraded confinement state is also observed. 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引用次数: 0

摘要

温德斯坦 7-X 恒星器(W7-X)中的低磁剪切使得通过构成岛-分流器的大岛来塑造分离矩阵成为可能,这可以用来获得各种磁配置,包括不同内部岛尺寸和位置的样本。为了研究构型对等离子体约束的影响,在最大等离子体密度为 8×1019m-2 的情况下,通过改变线圈电流来改变等离子体边界 5/4 和 5/6 值之间的旋转变换,并采用不同功率级别(2、4、6 MW)的电子回旋共振加热(ECRH)进行了构型扫描。在扫描的某些构型中还采用了中性束注入(NBI)加热,以产生密度斜坡并获得超出 X2 ECRH 截止值的高密度。在磁性配置中,5/5 和 5/6 岛链靠近分离矩阵,但仍位于最后一个封闭的通量面内,电子回旋发射显示,在 ECRH 加热等离子体建立阶段就已经出现了电子温度 Te 基座,这表明存在传输障碍,并且在放电后期,无论等离子体加热条件(如 NBI)如何变化,该障碍都会持续存在。传输屏障被随后的快速撞击打破,通过多种等离子体诊断技术观测到的撞击具有托卡马克边缘局部模式等特征,相应的撞击幅度和频率随等离子体压力而变化。传输屏障对等离子体约束的影响可以通过增加的核心 Te 曲线看出,这可能是这些配置中存储的二磁性能量总体增加约 10%的原因。在等离子体加热终止后,还观察到向退化约束状态的逆向过渡。这些观察结果表明,在低剪切力 W7-X 中,配置触发了高约束模式。这项工作的重点是在不同磁构型下出现的这种传输障碍及其与内部磁岛的关系。
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Electron transport barrier and high confinement in configurations with internal islands close to the plasma edge of W7-X
The low magnetic shear in the Wendelstein 7-X (W7-X) stellarator makes it feasible to shape the separatrix by the large islands constituting an island-divertor, and this can be exploited to access various magnetic configurations, including samples of different internal island sizes and locations. To investigate the configuration effects on the plasma confinement, a configuration scan was performed by changing the coil currents to vary the rotational transform between values 5/4 and 5/6 at the plasma boundary with different power levels (2, 4, 6 MW) of electron cyclotron resonance heating (ECRH) at a maximum plasma density of 8×1019m2. neutral beam injection (NBI) heating was also applied during some configurations of the scan to create a density ramp and access high densities beyond the X2 ECRH cutoff. For the magnetic configurations, where the 5/5 and 5/6 island chains were moved closer to separatrix but remaining inside the last closed flux surface, the electron cyclotron emission shows that an electron temperature, Te, pedestal develops already during ECRH heated plasma buildup phase indicating a transport barrier, and the barrier sustains irrespective of changed plasma heating conditions such as NBI in the later part of discharge. The transport barrier is broken by subsequent fast crashes, observed with multiple plasma diagnostics with characteristics such as tokamak edge localized modes, and the corresponding crash amplitude and frequency vary with plasma pressure. The impact of the transport barrier on plasma confinement can be seen through the increased core Te profile, which could be responsible for the overall increase in the stored diamagnetic energy by approximately 10% for these configurations. After the plasma heating is terminated, a backwards transition to a degraded confinement state is also observed. These observations indicate a configuration triggered high confinement mode in low shear W7-X. This work focuses on the occurrence of this transport barrier for different magnetic configurations and its relation to internal magnetic islands.
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来源期刊
Nuclear Fusion
Nuclear Fusion 物理-物理:核物理
CiteScore
6.30
自引率
39.40%
发文量
411
审稿时长
2.6 months
期刊介绍: Nuclear Fusion publishes articles making significant advances to the field of controlled thermonuclear fusion. The journal scope includes: -the production, heating and confinement of high temperature plasmas; -the physical properties of such plasmas; -the experimental or theoretical methods of exploring or explaining them; -fusion reactor physics; -reactor concepts; and -fusion technologies. The journal has a dedicated Associate Editor for inertial confinement fusion.
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