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首页> 外文期刊>Nuclear fusion >Non-inductive build-up of a hot plasma by X-wave ECH/ECCD to remove initial high loop-voltage from start-up of fusion tokamaks
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Non-inductive build-up of a hot plasma by X-wave ECH/ECCD to remove initial high loop-voltage from start-up of fusion tokamaks

机译：通过X波ECH / ECCD以非感应方式建立热等离子体，以消除聚变托卡马克装置启动时产生的初始高环路电压

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摘要

The possibility of non-inductive build-up of a hot plasma by X-wave ECH/ECCD to remove initial high loop-voltage stage from start-up of fusion tokamaks is theoretically investigated, using ITER parameters. There are two injection methods for X-wave ECH/ECCD in ITER start-up plasmas. The first is oblique X-wave injection from the low-field side, referred to as the DX method. For the low density start-up plasma at n_e ≈ 1.0 × 10~(19) m~(-3), the wave with ω/2π = 200 GHz and N_‖ ～ 0.6 is damped away via cyclotron resonance absorption before encountering the cyclotron cutoff layer when the electron temperature is as high as T_e > 170 eV. The wave power is deposited into the resonance electrons of which parallel velocity is as fast as v_‖ > 2(2T_e/m)~(1/2), which enables an efficient ECCD. The second method is oblique O-wave injection from the low-field side, referred to as the OX method. The waves pass through the ECR layer with negligible power deposition when T_e < 400 eV and are mode-converted into oblique X-waves upon reflection on the inboard wall. The X-waves propagate toward the ECR layer without cutoff, and are cyclotron-damped away even when the temperature is as low as T_e ～ 7 eV. The OX method is appropriate for the initial open field stage and transition stage of the discharge, while the DX method is appropriate for the final tokamak stage, where T_e is high. Discussions are given on the choice of appropriate B_v and location of ECR layer for initiation of closed flux surfaces. Nine model plasmas from an initial open field plasma to a final hot tokamak plasma, consisting of a series of snapshots of a build-up discharge, are generated using an equilibrium theory, enabling estimation of required RF power to drive the current. These investigations suggest that an injection power P_(rf) ～ 4 MW could build up a hot plasma with I_p = 205 kA, n_(e0) = 1.2 × 10~(19) m~(-3), T_(e0) = 2 keV, a = 1 m and R_0 = 5.1 m.
机译：理论上，使用ITER参数研究了通过X波ECH / ECCD进行非感应性聚积的可能性，以消除聚变托卡马克装置启动时的初始高环路电压级。在ITER启动等离子体中，有两种X射线ECH / ECCD注入方法。第一种是从低场侧倾斜的X波注入，称为DX方法。对于n_e≈1.0×10〜（19）m〜（-3）的低密度启动等离子体，在遇到回旋加速器之前，通过回旋共振吸收将ω/2π= 200 GHz和N_‖〜0.6的波衰减掉电子温度高达T_e> 170 eV时的截止层。波功率被沉积到谐振电子中，其平行速度高达v_1> 2（2T_e / m）〜（1/2），从而实现了高效的ECCD。第二种方法是从低场侧倾斜O波注入，称为OX方法。当T_e <400 eV时，这些波以微不足道的功率沉积通过ECR层，并在内侧壁上反射后被模式转换为倾斜的X波。 X波在没有截止的情况下向ECR层传播，即使温度低至T_e〜7 eV，也会被回旋加速器衰减。 OX方法适用于放电的初始空场阶段和过渡阶段，而DX方法适用于T_e高的最终托卡马克阶段。讨论了适当的B_v的选择和ECR层的位置，以启动封闭的磁通表面。使用平衡理论生成了从初始开场等离子体到最终热托卡马克等离子体的九种模型等离子体，其中包括一系列堆积放电的快照，从而可以估算驱动电流所需的RF功率。这些研究表明，注入功率P_（rf）〜4 MW可以建立热等离子体，I_p = 205 kA，n_（e0）= 1.2×10〜（19）m〜（-3），T_（e0）= 2 keV，a = 1 m，R_0 = 5.1 m。

著录项

  • 来源
    《Nuclear fusion》 |2018年第1期|016037.1-016037.18|共18页
  • 作者

    T. Maekawa; M. Uchida; H. Tanaka;

  • 作者单位

    Graduate School of Energy Science, Kyoto University, Kyoto 606-8502, Japan;

    Graduate School of Energy Science, Kyoto University, Kyoto 606-8502, Japan;

    Graduate School of Energy Science, Kyoto University, Kyoto 606-8502, 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

    non-inductive start-up; ECH/ECCD; X-wave;

    机译：非感应启动;ECH / ECCD;X波;

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