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Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation

机译:NSTX等离子面对部件上的锂涂层及其对边界控制,堆芯等离子性能和操作的影响

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摘要

NSTX high power divertor plasma experiments have used in succession lithium pellet injection (LPI), evaporated lithium, and injected lithium powder to apply lithium coatings to graphite plasma facing components. In 2005, following the wall conditioning and LPI, discharges exhibited edge density reduction and performance improvements. Since 2006, first one, and now two lithium evaporators have been used routinely to evaporate lithium onto the lower divertor region at total rates of 10-70mg/min for periods 5-10min between discharges. Prior to each discharge, the evaporators are withdrawn behind shutters. Significant improvements in the performance of NB1 heated divertor discharges resulting from these lithium depositions were observed. These evaporators are now used for more than 80% of NSTX discharges. Initial work with injecting fine lithium powder into the edge of NBI heated deuterium discharges yielded comparable changes in performance. Several operational issues encountered with lithium wall conditions, and the special procedures needed for vessel entry are discussed. The next step in this work is installation of a liquid lithium divertor surface on the outer part of the lower divertor.
机译:NSTX高功率偏滤器等离子体实验已相继使用了锂颗粒注入(LPI),蒸发的锂和注入的锂粉,以将锂涂层应用于面向石墨等离子体的部件。在2005年,在进行墙面调节和LPI之后,放电表现出边缘密度降低和性能改善的趋势。自2006年以来,通常使用第一个锂蒸发器,现在使用两个锂蒸发器,以10-70mg / min的总速率将锂蒸发到下偏滤器区域,每次放电之间间隔5-10min。在每次排放之前,将蒸发器撤回百叶窗后面。观察到由这些锂沉积导致的NB1加热的偏滤器放电的性能得到了显着改善。现在,这些蒸发器用于80%以上的NSTX排放。最初的工作是将细小的锂粉注入NBI加热的氘气排放的边缘,从而产生了可比的性能变化。讨论了锂壁条件遇到的几个操作问题,以及进入容器所需的特殊程序。这项工作的下一步是在下分流器的外部安装液态锂分流器表面。

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  • 来源
    《Fusion Engineering and Design》 |2010年第6期|p.865-873|共9页
  • 作者单位

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Purdue University, School of Nuclear Engineering, West Lafayette, IN 47907, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Sandia National Laboratories, Albuquerque, NM 87185, USA;

    Oak Ridge National Laboratory. Oak Ridge, TN 37831, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    University of Washington. Seattle, WA 98195, USA;

    Columbia University, New York NY 10027, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Lawrence Livermore National Laboratory, Livermore, CA 94551, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, USA;

    Princeton Plasma Physics Laboratory, PO Box 451, Princeton, N] 08543, 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

    lithium; lithium wall fusion regime; recycling; plasma wall interactions; divertors; spherical torus;

    机译:锂;锂壁熔融机制;回收;血浆壁相互作用;转向器球形环面;
  • 入库时间 2022-08-18 00:39:45

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