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Overview of KSTAR initial operation

机译:KSTAR初始操作概述

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摘要

Since the successful first plasma generation in the middle of 2008, three experimental campaigns were successfully made for the KSTAR device, accompanied with a necessary upgrade in the power supply, heating, wall-conditioning and diagnostic systems. KSTAR was operated with the toroidal magnetic field up to 3.6 T and the circular and shaped plasmas with current up to 700 kA and pulse length of 7 s, have been achieved with limited capacity of PF magnet power supplies. The mission of the KSTAR experimental program is to achieve steady-state operations with high performance plasmas relevant to ITER and future reactors. The first phase (2008-2012) of operation of KSTAR is dedicated to the development of operational capabilities for a super-conducting device with relatively short pulse. Development of start-up scenario for a super-conducting tokamak and the understanding of magnetic field errors on start-up are one of the important issues to be resolved. Some specific operation techniques for a super-conducting device are also developed and tested. The second harmonic pre-ionization with 84 and 110 GHz gyrotrons is an example. Various parameters have been scanned to optimize the pre-ionization. Another example is the ICRF wall conditioning (ICWC), which was routinely applied during the shot to shot interval. The plasma operation window has been extended in terms of plasma beta and stability boundary. The achievement of high confinement mode was made in the last campaign with the first neutral beam injector and good wall conditioning. Plasma control has been applied in shape and position control and now a preliminary kinetic control scheme is being applied including plasma current and density. Advanced control schemes will be developed and tested in future operations including active profiles, heating and current drives and control coil-driven magnetic perturbation.
机译:自从2008年中期成功生产出第一批等离子体以来,针对KSTAR设备成功进行了三项实验,同时对电源,供暖,壁式调节和诊断系统进行了必要的升级。 KSTAR在高达3.6 T的环形磁场下运行,并且在功率有限的PF磁体电源的情况下,可实现电流高达700 kA,脉冲长度为7 s的圆形和成形等离子体。 KSTAR实验计划的任务是使用与ITER和未来反应堆有关的高性能等离子体实现稳态运行。 KSTAR运行的第一阶段(2008-2012年)致力于开发具有相对短脉冲的超导设备的运行能力。超导托卡马克启动方案的开发以及对启动时磁场误差的理解是需要解决的重要问题之一。还开发并测试了一些用于超导设备的特定操作技术。一个示例是使用84 GHz和110 GHz的回旋管进行二次谐波预电离。扫描了各种参数以优化预电离。另一个示例是ICRF墙面调节(ICWC),通常在每次射击间隔期间应用。等离子体操作窗口在血浆β和稳定性边界方面得到了扩展。在上一个战役中,第一个中性射束注入器和良好的壁面调节功能实现了高限制模式。等离子体控制已应用于形状和位置控制,现在正在应用初步的动力学控制方案,包括等离子体电流和密度。先进的控制方案将在未来的运行中进行开发和测试,包括有源曲线,加热和电流驱动以及控制线圈驱动的磁扰动。

著录项

  • 来源
    《Nuclear fusion》 |2011年第9期|p.72-83|共12页
  • 作者单位

    National Fusion Research Institute, Daejeon, Korea;

    National Fusion Research Institute, Daejeon, Korea;

    National Fusion Research Institute, Daejeon, Korea;

    National Fusion Research Institute, Daejeon, Korea;

    National Fusion Research Institute, Daejeon, Korea;

  • 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
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