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The lower hybrid current drive system for steady-state operation of the Vulcan tokamak conceptual design

机译:适用于Vulcan托卡马克概念设计的较低混合电流驱动系统,用于稳态操作

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摘要

The steady-state current drive system for the Vulcan tokamak concept has been designed, taking into account requirements of high field, small size, and high operational wall temperature (B_0 = 7 T, R_0 = 1.2 m, T_(wall) > 800 K). This lower hybrid current drive system allows steady-state operation by utilizing high field side launch, high RF source frequency (8 GHz), and dedicated current drive ports. An iterative MHD and current drive solver is used to determine the ideal launching spectra and location to assure strong single pass absorption. It is found that with nominal Vulcan operational parameters (n_e≈4× 10~(20)m~(-3), T_e≈2.8 keV, I_9 = 1.7 MA, P_(LHCD) = 19.8 MW) bootstrap currents of ~70% and lower hybrid current drive efficiencies of 1.16 x 10~(19) A W m~2 could be achieved. The optimized solution yielded advanced tokamak profiles with q values on-axis above 2. A conceptual design of the system is presented, which takes into account space, power, cooling, and launched spectrum requirements. The system is found to be compatible with the vacuum vessel design and requires cooling power of <1 MW per waveguide bundle.
机译:设计了用于Vulcan托卡马克概念的稳态电流驱动系统,并考虑了高场,小尺寸和高运行壁温的要求(B_0 = 7 T,R_0 = 1.2 m,T_(壁)> 800 K )。这种较低的混合电流驱动系统通过利用高场侧发射,高RF源频率(8 GHz)和专用电流驱动端口,可以实现稳态操作。迭代的MHD和电流驱动求解器用于确定理想的发射光谱和位置,以确保强大的单程吸收。发现在标称Vulcan操作参数下(n_e≈4×10〜(20)m〜(-3),T_e≈2.8keV,I_9 = 1.7 MA,P_(LHCD)= 19.8 MW)自举电流为〜70%混合电流驱动效率可达到1.16 x 10〜(19)AW m〜2。优化的解决方案产生了q值在2以上的高级托卡马克轮廓。提出了系统的概念设计,其中考虑了空间,功率,冷却和发射频谱的要求。发现该系统与真空容器设计兼容,并且每个波导束要求的冷却功率<1 MW。

著录项

  • 来源
    《Fusion Engineering and Design》 |2012年第3期|p.215-223|共9页
  • 作者单位

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

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

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

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

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA, 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; steady-state; fusion development; lower hybrid; current drive;

    机译:托卡马克稳定状态;融合发展;低杂种当前驱动器;
  • 入库时间 2022-08-18 00:39:15

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