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Liquid tin interactions with ISTTOK plasmas

机译:液态锡与ISTTOK等离子体的相互作用

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Materials such as lithium, gallium and tin have been proposed as candidates for liquid metals plasma facing components. The properties of these materials introduce novel methods to cope with the high power loads on the divertor region of nuclear fusion reactors. Although several results have been reported using lithium less experiments were done using gallium or tin. With the purpose of comprehending the impact of the utilisation of tin on a tokamak's plasma performance it was deemed relevant to perform a series of experiments with particular emphasis on plasma contamination. In this work several diagnostics, such as H-alpha, bolometry, visible spectroscopy and electrostatic probes are used to characterise the interaction of plasmas with tin samples and impact this material had on the tokamak discharge performance. Liquid tin samples were exposed in the ISTTOK's edge and subject to deuterium plasmas. The sample's surface temperature was monitored by pyrometry from which plasma induced heat load was inferred. Heat loads in excess of 300 kWm(-2) was regularly observed which are in agreement with Langmuir probe analysis. H-alpha, bolometry and plasma resistivity were used as proxies for plasma performance and these were found to remain unchanged throughout the sample exposure. The radial impurity content across the plasma column of ISTTOK is characterised by spectroscopic measurements of the Sn-II line 579.88 nm. The line intensity was found to exponentially decrease towards the plasma center with a decay length of approximate to 2.3 mm. These results suggest that, under specific experimental conditions, liquid tin had a negligible impact in the plasma performance of ISTTOK discharges.
机译:已经提出诸如锂,镓和锡的材料作为液态金属等离子体面对部件的候选物。这些材料的性能引入了新颖的方法来应对核聚变反应堆分流器区域的高功率负载。尽管已报道了使用锂的一些结果,但使用镓或锡的实验却很少。为了理解锡的利用对托卡马克等离子体性能的影响,认为进行一系列特别关注等离子体污染的实验是有意义的。在这项工作中,使用了一些诊断程序,例如H-alpha,辐射热分析,可见光谱和静电探针,来表征等离子体与锡样品的相互作用,以及这种材料对托卡马克放电性能的影响。液态锡样品暴露在ISTTOK的边缘,并受到氘等离子体的影响。通过高温测定法监测样品的表面温度,由此推断出等离子体诱导的热负荷。定期观察到超过300 kWm(-2)的热负荷,这与Langmuir探针分析相符。 H-alpha,辐射热测定法和血浆电阻率用作血浆性能的代理,发现在整个样品暴露过程中它们保持不变。 ISTTOK等离子体柱上的径向杂质含量通过光谱法测量Sn-II线579.88 nm来表征。发现线强度朝向等离子体中心呈指数下降,衰减长度约为2.3 mm。这些结果表明,在特定的实验条件下,液态锡对ISTTOK放电的等离子体性能的影响可忽略不计。

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