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Recent results from divertor and scrape-off layer studies at JET

机译:JET的偏滤器和刮除层研究的最新结果

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摘要

Recent progress in the study of divertor and scrape-off layer plasma phenomena in JET is reviewed. Three pumped divertors (Mark I, Mark IIA/AP and Mark IIGB) have been installed and exploited under reactor relevant conditions. With increased divertor closure, the particle exhaust rate has increased and neutral compression factors of >100 have been obtained with the Mark IIGB divertor. Helium enrichment factors of >0.2 have been measured under a wide range of conditions and satisfy the minimum requirements for ITER. Excellent power handling has been demonstrated in all divertor configurations. Fast infrared camera measurements exhibited broad deposition profiles during type I ELMs and energy densities of ~0.12 MJ/m~2 which extrapolate to unacceptable levels for ITER. During the recent DT experiments, the co-deposition of tritium on cold shadowed surfaces in the inner divertor was identified as an important form of long term tritium retention. This has serious implications for the divertor design and tritium inventory in a next step tokamak. Core plasma purity has not improved with enhanced divertor closure or decreased main chamber neutral pressure. Studies of the chemical sputtering yield showed a dependence on surface temperature and hydrogen isotope. This accounts for the observation of increased carbon impurity production in Mark II (at 500 K) relative to Mark I (at 300 K). The variation of the disruptive (L mode) density limit appears to be more strongly dependent on the local impurity production rate than on the divertor geometry. Significant progress has been made in the study of divertor detachment, and volume recombination has been spectroscopically identified. With increasing isotope mass, detachment and the disruptive density limit occur at lower main plasma density, as predicted by the EDGE2D/NIMBUS codes. Using differential gas fuelling in the Mark IIGB divertor, it was possible to modify the in--out asymmetry of the divertor plasma parameters and energy deposition for the first time.
机译:综述了JET中偏滤层和刮除层等离子体现象研究的最新进展。已经安装了三台抽油分流器(Mark I,Mark IIA / AP和Mark IIGB),并在与反应堆有关的条件下开采。随着分流器关闭程度的提高,颗粒排放速率增加,Mark IIGB分流器获得的中性压缩系数> 100。在广泛的条件下测得的氦富集系数> 0.2,并满足ITER的最低要求。在所有偏滤器配置中都已证明了出色的动力处理能力。快速红外热像仪的测量显示出I型ELM期间的沉积分布较宽,能量密度约为0.12 MJ / m〜2,这对于ITER来说是无法接受的。在最近的DT实验中,identified在内部分流器冷阴影表面上的共沉积被确定为term长期保留的重要形式。这对下一步托卡马克中的分流器设计和tri存量具有严重影响。随着分流器关闭的增加或主腔室中性压力的降低,核心等离子体的纯度并未得到改善。化学溅射产率的研究表明,它与表面温度和氢同位素有关。这说明观察到Mark II(在500 K下)相对于Mark I(在300 K下)增加了碳杂质的产生。破坏性(L模式)密度极限的变化似乎比偏滤器的几何形状更强烈地取决于局部杂质的产生速率。在偏滤器分离的研究中已经取得了重大进展,并且通过光谱鉴定了体积重组。正如EDGE2D / NIMBUS代码所预测的,随着同位素质量的增加,在较低的主等离子体密度下会发生分离和破坏性密度极限。在Mark IIGB偏滤器中使用差分气体供油,首次可以改变偏滤器等离子体参数的进出不对称性和能量沉积。

著录项

  • 来源
    《Nuclear fusion》 |1999年第11y期|p.1751-1762|共12页
  • 作者

    JET Team;

  • 作者单位
  • 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 原子核物理学、高能物理学;
  • 关键词

  • 入库时间 2022-08-18 00:32:42

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