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Pedestal structure and stability in H-mode and I-mode: a comparative study on Alcator C-Mod

机译:H模式和I模式下的基座结构和稳定性:Alcator C-Mod的比较研究

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摘要

New experimental data from the Alcator C-Mod tokamak are used to benchmark predictive modelling of the edge pedestal in various high-confinement regimes, contributing to greater confidence in projection of pedestal height and width in ITER and reactors. ELMy H-modes operate near stability limits for ideal peeling-ballooning modes, as shown by calculations with the ELITE code. Experimental pedestal width in ELMy H-mode scales as the square root of ss_(poI) at the pedestal top, i.e. the dependence expected from theory if kinetic ballooning modes (KBMs) were responsible for limiting the pedestal width. A search for KBMs in experiment has revealed a short-wavelength electromagnetic fluctuation in the pedestal that is a candidate driver for inter-edge localized mode (ELM) pedestal regulation. A predictive pedestal model (EPED) has been tested on an extended set of ELMy H-modes from C-Mod, reproducing pedestal height and width reasonably well across the data set, and extending the tested range of EPED to the highest absolute pressures available on any existing tokamak and to within a factor of three of the pedestal pressure targeted for ITER. In addition, C-Mod offers access to two regimes, enhanced D-alpha (EDA) H-mode and I-mode, that have high pedestals, but in which large ELM activity is naturally suppressed and, instead, particle and impurity transport are regulated continuously. Pedestals of EDA H-mode and I-mode discharges are found to be ideal magnetohydrodynamic (MHD) stable with ELITE, consistent with the general absence of ELM activity. Invocation of alternative physics mechanisms may be required to make EPED-like predictions of pedestals in these kinds of intrinsically ELM-suppressed regimes, which would be very beneficial to operation in burning plasma devices.
机译:来自Alcator C-Mod托卡马克的新实验数据用于在各种高约束条件下对边缘基座的预测建模进行基准测试,从而有助于增强对ITER和反应堆中基座高度和宽度的投影的信心。 ELMy H模式在接近稳定极限的范围内工作,以实现理想的剥离气球模式,如使用ELITE代码进行的计算所示。 ELMy H模式下的实验基座宽度缩放为基座顶部ss_(poI)的平方根,即,如果动力气球模式(KBM)限制了基座宽度,则理论上的依赖关系就可以确定。在实验中对KBM的搜索揭示了基座中的短波电磁波动,这是边缘间局部模式(ELM)基座调节的候选驱动因素。已在C-Mod的ELMy H模式扩展集上测试了预测基座模型(EPED),在整个数据集中合理地再现了基座高度和宽度,并将EPED的测试范围扩展到了可用的最高绝对压力任何现有的托卡马克,且其温度应为ITER目标基座压力的三倍。此外,C-Mod提供了两种方式,即增强的D-alpha(EDA)H模式和I模式,具有高基座,但是自然抑制了大ELM活性,而可以通过颗粒和杂质传输持续监管。发现EDA H-模式和I-模式放电的基座是理想的具有ELITE稳定的磁流体动力学(MHD),这与普遍缺乏ELM活性相一致。在这类固有的ELM抑制方案中,可能需要调用替代物理机制来做出类似EPED的基座预测,这对燃烧等离子体设备非常有益。

著录项

  • 来源
    《Nuclear fusion》 |2013年第4期|043016.1-043016.8|共8页
  • 作者单位

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    General Atomics, San Diego, CA 92186, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Princeton Plasma Physics Laboratory, Princeton, NJ, 08543 USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    General Atomics, San Diego, CA 92186, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    General Atomics, San Diego, CA 92186, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, MA 02139, USA;

    Lawrence Livermore National Laboratory, Livermore, CA 94550,USA;

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  • 正文语种 eng
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