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Studies of Li sputtering and particle recycling in glow discharges and in TJ-II

机译:辉光放电和TJ-II中Li溅射和颗粒回收的研究

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摘要

Lithium sputtering is studied at TJ-II with lithiated, boron coated walls. As reported previously, the sputtering yield measured in H plasmas was found to be significantly lower than expected, based on laboratory experiments and TRIM code calculations. The edge temperature dependence of the yield could be consistent with either an energy threshold far exceeding the corresponding pure lithium threshold, or with a strong perturbation of the impinging ion energies. The material mixing effect, one of the candidates for explaining the observed behavior, was studied by depositing boron on the Li layer. Also, particle retention and release was investigated in H/He plasmas in this very low recycling scenario. The release of either species in the opposite plasma was studied in different plasma conditions as well as in glow discharge (GD) plasmas. In He GD plasmas, the I/V characteristics of lithiated stainless steel electrodes were found to be anomalous, in spite of the fact that the dependence of sputtering on the incident particle energy agreed reasonably with expectations. The possible implications of these phenomena for the interaction of reactor plasmas with lithium elements are addressed.
机译:在TJ-II处研究了锂化溅射过程,该过程具有锂化,硼涂层壁。如前所述,根据实验室实验和TRIM代码计算,发现在H等离子体中测得的溅射产率明显低于预期。产率的边缘温度依赖性可以与远远超过相应的纯锂阈值的能量阈值或与撞击离子能量的强烈扰动相一致。通过在Li层上沉积硼,研究了材料混合效应,该材料混合效应是解释观察到的行为的候选者之一。同样,在这种非常低的回收率情况下,在H / He等离子体中研究了颗粒保留和释放。在不同的等离子体条件下以及辉光放电(GD)等离子体中研究了在相对等离子体中两种物质的释放。在He GD等离子体中,尽管溅射对入射粒子能量的依赖性与预期合理吻合,但发现锂化不锈钢电极的I / V特性异常。解决了这些现象对反应堆等离子体与锂元素相互作用的可能影响。

著录项

  • 来源
    《Fusion Engineering and Design》 |2012年第10期|p.1741-1746|共6页
  • 作者单位

    National Laboratory for Fusion Association Euratom/Ciemat, Av. Complutense 22,28040 Madrid, Spain;

    National Laboratory for Fusion Association Euratom/Ciemat, Av. Complutense 22,28040 Madrid, Spain;

    National Laboratory for Fusion Association Euratom/Ciemat, Av. Complutense 22,28040 Madrid, Spain;

    National Laboratory for Fusion Association Euratom/Ciemat, Av. Complutense 22,28040 Madrid, Spain;

    National Laboratory for Fusion Association Euratom/Ciemat, Av. Complutense 22,28040 Madrid, Spain;

  • 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; sputtering; first wall material; recycling; TJ-II;

    机译:锂;溅射第一壁材料;回收;TJ-II;
  • 入库时间 2022-08-18 00:39:15

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