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Mitigation of large amplitude edge-localized modes by resonant magnetic perturbations onLHD

机译:通过LHD上的共振磁扰动缓解大幅度边缘局域模

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摘要

In the Large Helical Device (LHD), H-mode plasmas are produced, having large amplitude edge-localized modes (ELMs) which are induced by resistive interchange modes (RICs) at the l/2π = 1 rational surface near the foot of the edge transport barrier (ETB). These large ELMs expel a large fraction of plasma stored energy, up to 20% of the stored energy (Wp). The ETB and the l/2π = 1 surface are thought to be in the stochastic field region (SFR) generated intrinsically in three-dimensional magnetic configuration on LHD, because plasma shielding effects for such stochastic fields are not significant due to low electrical conductivity σ and moderate angular frequency of plasma rotation ω in the ETB and the field penetration depth is estimated to be comparable to the ETB width. Even if the ETB is in such intrinsic SFR where electron mean free path is much shorter than the connection length, large amplitude ELMs are excited. Such ELMs were mitigated by externally applied m = 1 = 1 resonant magnetic perturbations (RMPs), for the first time, in a stellarator/helical plasma, where m and n are the poloidal and toroidal mode numbers, respectively. The RMPs reduce the amplitude, enhancing the repetition frequency significantly. The energy loss fraction ΔW_P/W_P is reduced less than ~5% by the mitigation. This mitigation is realized without terminating the H-mode and large penalty to global energy confinement. The RMPs preferentially decrease electron density in ETB indicating enhanced particle transport, while electron and ion temperature profiles are nearly unchanged. Plasma shielding effects for the applied RMPs is also not significant because of low σ and moderate ω in ETB. Noticeable decrease in the gradients of electron density and pressure in the ETB and also at the l/2π = 1 surface is induced by the penetration of the applied RMPs. Enhanced ELM frequency indicates that MHD stability of ETB for RICs is degraded by RMPs. Potential mechanisms of ELM mitigation on LHD are discussed.
机译:在大型螺旋装置(LHD)中,产生的H型等离子体具有大幅度的边沿局域模(ELM),这是由电阻交换模(RIC)在l /2π= 1有理表面附近的感应面诱导的。边缘传输屏障(ETB)。这些大的ELM会排出大部分的等离子体存储能量,最高可达存储能量(Wp)的20%。 ETB和l /2π= 1表面被认为是在LHD上以三维磁性构型固有生成的随机场区域(SFR),因为由于低电导率σ,对于这种随机场的等离子体屏蔽效果不明显ETB中等离子旋转ω的适中角频率ω和场穿透深度估计与ETB宽度相当。即使ETB在电子平均自由程比连接长度短得多的本征SFR中,也会激发大振幅的ELM。首次在恒星/螺旋等离子体中,通过外部施加m = 1 / n = 1共振磁扰动(RMP)减轻了此类ELM,其中m和n分别是极谱和环模数。 RMP降低了幅度,大大提高了重复频率。通过缓解,能量损失分数ΔW_P/ W_P降低了不到5%。可以在不终止H模式的情况下实现这种缓解,并且不会对全局能量限制造成较大损失。 RMP优先降低ETB中的电子密度,表明粒子传输增强,而电子和离子温度曲线几乎不变。由于ETB中的σ低且ω中等,因此对所施加的RMP的等离子体屏蔽效果也不显着。所施加的RMP的渗透会导致ETB以及l /2π= 1表面的电子密度和压力梯度明显下降。增强的ELM频率表明RMP对RIC的ETB的MHD稳定性会降低。讨论了ELM缓解LHD的潜在机制。

著录项

  • 来源
    《Nuclear fusion》 |2014年第3期|033001.1-033001.14|共14页
  • 作者单位

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    Faculty of Energy Science, Kyoto University, Kyoto, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    Department of Fusion Science, The Graduate University for Advanced Study, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

    National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    edge-localized modes; H-mode; resonant magnetic perturbations; stochastic fields; plasma shielding; stellarators and helicals; resistive interchange modes;

    机译:边缘定位模式H模式共振磁扰动随机领域等离子屏蔽恒星器和螺旋线;电阻互换模式;
  • 入库时间 2022-08-18 00:42:52

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