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Increased core ion temperatures in high-beta advanced scenarios in ASDEX upgrade

机译:在Asdex升级中增加了高β高级情景中的核心离子温度

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摘要

Non-inductive advanced tokamak scenarios are a possible way for future nuclear fusion power plants to run in non-pulsed operation. In these scenarios, the ohmic current is replaced on the one hand with a current driven by external sources such as NBI and ECRH and on the other hand with a substantial bootstrap-current. The bootstrap current is produced in the presence of pressure gradients. This means, to increase the bootstrap-current-fraction, it is advantageous to have regions where ITG turbulence is reduced. To be able to extrapolate from non-inductive scenarios done in smaller present day devices, it is important to have transport models that allow the user to reproduce these experiments and accurately capture the physics behind the reduction of turbulent transport. One commonly used model is the quasi-linear gyrofluid transport model TGLF, which is well tested in standard scenarios. However, in the past, TGLF has failed to reproduce the peaked ion temperature profiles of certain advanced scenario shots. In this article, progress in overcoming this issue of TGLF will be discussed. Results of a recent publication are reproduced in which TGLF was able to match the experimentally measured peaked ion temperature profiles. In these simulations, we find the E × B-shear to play an important role in the reduction of ITG turbulence. In contrast to that, experimentally we find the E × B-shear to have no effect on the formation of such regions of decreased turbulent transport. This finding is in line with simulations using the gyrokinetic code GENE. A new approach of modelling these advanced scenarios in TGLF is introduced, allowing us to match the peaked ion temperature profiles without depending on the E × B-shear.
机译:非归纳高级Tokamak情景是未来核聚变电厂在非脉冲操作中运行的可能方法。在这些场景中,欧姆电流在一方面替换,其中电流由外部源(如NBI和ECRH)驱动,另一方面具有大量自动启动电流。引导电流在存在压力梯度时产生。这意味着增加自举电流分数,有利于具有ITG湍流的区域减少。为了能够从较小的当天设备中完成的非归纳情景外推,重要的是具有允许用户再现这些实验并准确地捕获湍流运输减少后的物理学的运输模型非常重要。一个常用的模型是准线性陀螺流体传输模型TGLF,其在标准场景中进行了很好的测试。然而,在过去,TGLF未能再现某些高级场景射击的峰值离子温度谱。在本文中,将讨论克服这一问题的TGLF的进展。再现最近发表的结果,其中TGLF能够匹配实验测量的峰值离子温度谱。在这些模拟中,我们发现E×B剪切在减少ITG湍流中发挥重要作用。与此相反,实验我们发现E×B剪切对形成这种降低的湍流运输区域的形成没有影响。该发现符合使用陀螺码基因的模拟。引入了模拟TGLF中这些高级场景的新方法,允许我们匹配峰值离子温度型材而不取决于E×B剪切。

著录项

  • 来源
    《Nuclear fusion》 |2020年第8期|082005.1-082005.9|共9页
  • 作者单位

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany Ludwig-Maximilian-Universitaet Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

    Max-Planck-Institut fuer Plasmaphysik 85748 Garching bei Muenchen Germany;

  • 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

    advanced tokamak; plasma transport; TGLF; exb-shear; ion temperature;

    机译:高级托卡马克;等离子体运输;tglf;exb剪切;离子温度;

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