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Avoidance of impurity-induced current quench using lower hybrid current drive

机译:使用较低的混合电流驱动避免杂质引起的电流失超

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摘要

This work reports observations of a tokamak plasma that experienced a thermal quench due to a large, transient high-Z influx but avoided a current quench. This is argued to be caused by the presence of lower hybrid range of frequency (LHRF) waves that sustain a non-thermal, current-carrying electron population. In Alcator C-Mod L-mode plasmas at I-p = 450 kA, (n) over bar (e) = 0.5 x 10(20) m(-3), nearly all of the current can be sustained non-inductively by injecting similar or equal to 700 kW of LHRF power at 4.6 GHz and n(parallel to) = 1.9. A sudden influx of a large amount of tungsten, n(z)(e) similar or equal to 0.0044, triggers a cooling wave that propagates at 2-3 m s(-1) all the way into the core, dropping on-axis T-e from 3 keV to temperatures less than measurement floor of 50 eV. An off-axis reheat begins after 100 ms, but T-e profiles remain hollow for 300-350 ms after the injection. Throughout this temperature evolution, the plasma density, current and shape remain unchanged to within 10%. Following the expulsion of the tungsten, the plasma returns to its baseline conditions and the plasma ends as planned with a controlled current ramp-down. Energy balance analysis shows the LHRF power continues to be absorbed in the plasma after the thermal quench, as a significant fraction of it is needed to be consistent with radiated power measurements. Examination of current relaxation time, T-R, and fast-electron slowing down time, T-S, indicate the LHRF must contribute to driving current, despite the low temperatures, as the current remains nominally stationary despite T-R 5 ms and T-S 50 ms for relativistic electrons. These measurements represent an important existence proof of a possible technique for avoidance of disruptions caused by sudden, unplanned influx of impurities in the form of dust or flakes of high-Z wall material. Implications and suggestions for future experimental and modeling and simulation work are summarized.
机译:这项工作报告了对托卡马克等离子体的观察结果,该等离子体由于大量的瞬时高Z流入而经历了热猝灭,但避免了电流猝灭。据认为,这是由于存在较低的混合频率范围(LHRF)的电波所致,这些电波维持了非热的载流电子。在Ip = 450 kA的Alcator C-Mod L模式等离子体中,(n)超过bar(e)= 0.5 x 10(20)m(-3),通过注入类似的电流几乎可以无感地维持所有电流等于4.6 GHz且n(平行)= 1.9时的700 kW LHRF功率。突然涌入大量钨,n(z)/ n(e)近似或等于0.0044,触发冷却波,该冷却波以2-3 ms(-1)的方式一直传播到堆芯,并在以下位置下降: Te轴从3 keV到低于测量底面50 eV的温度。离轴再加热在100毫秒后开始,但T-e型材在注入后300-350毫秒内保持中空。在整个温度变化过程中,等离子体密度,电流和形状均保持在10%以内。钨被排出后,等离子体返回到其基线状态,等离子体按计划在受控电流下降的情况下结束。能量平衡分析表明,热淬灭后LHRF功率继续在等离子体中吸收,因为需要很大一部分才能与辐射功率测量值保持一致。对电流弛豫时间TR和快速电子减速时间TS的检查表明,尽管温度较低,但LHRF必须有助于驱动电流,尽管相对论而言,尽管TR <5 ms和TS <50 ms,电流仍保持名义上稳定电子。这些测量结果代表了一种可能的技术的重要存在证据,该技术可避免因突然或计划外的高Z壁材料粉尘或薄片状杂质的意外流入而引起的中断。总结了对未来实验,建模和仿真工作的启示和建议。

著录项

  • 来源
    《Nuclear fusion》 |2019年第6期|066003.1-066003.12|共12页
  • 作者单位

    Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA;

    Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

    MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA;

  • 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

    tokamak; disruption; impurity; lower hybrid; runaway electron;

    机译:托卡马克;扰动;杂质;低杂化;电子失控;
  • 入库时间 2022-08-18 04:20:08

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