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Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry

机译:在西方等离子体放电后排出氘和氦气分散:延迟D〜HE转换实验期间用阈值电离质谱进行研究

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Threshold ionization mass spectrometry (TIMS) is one of two methods envisioned in ITER to quantify the helium (He) fusion product in the exhaust pumping lines during plasma discharges. We present the first demonstration of another potential application of TIMS in a tokamak environment, namely, the analysis of deuterium (D) and He outgassing following a plasma discharge i.e. during the post-discharge. This method has been tested with sub-second temporal resolution in WEST during its first He plasma discharges in the so-called He changeover experimental campaign. The calibration method of TIMS using a D plasma discharge is presented while the uncertainties related to TIMS during rapid pressure variations, i.e. upon plasma breakdown and plasma termination, are discussed. The first results obtained with TIMS during consecutive D and He plasma discharges in the full tungsten (W) tokamak WEST are reported. It is found that the time evolutions for He and D outgassing in the post-discharge are markedly different. On one hand, He outgassing is instantaneous and decays within 60?s until the He signal gets below detection level. On the other hand, D outgassing can reach a maximum up to several tens of seconds after the termination of the plasma and this outgassing can last for about 10?min. These striking differences should be related to different retention and outgassing from WEST plasma facing components, presently constituted of actively-cooled ITER-like W units and inertially cooled W-coated graphite. Potential mechanisms at the origin of the different outgassing behavior for D and He in W plasma facing components are discussed in light of a systematic analysis of the He and D gas balance and a macroscopic rate equation modeling of the D outgassing from the divertor strike points.
机译:阈值电离质谱(TIMS)是在等离子体放电期间在排气管线中量化排气泵送线中的氦气(HE)融合产物的两种方法之一。我们首次展示了在Tokamak环境中的TIMS的另一个潜在应用,即氘(D)的分析,并在等离子体放电后除了放电后。在西部的第一个他的第一次等离子体放电时,​​在西部的次级时间分辨率在所谓的HE转换实验活动中进行了测试。讨论了使用D等离子体放电的校准方法,同时讨论了与速度快速变化期间的时间相关的不确定性,即在等离子体击穿和等离子体终端时。报道了用连续D和HE钨(W)托卡马克斯西部的连续D和血浆排出获得的第一个结果。结果发现,后放电后他和D分散的时间变化显着不同。一方面,他的突出是瞬间的,在60?s之内衰减,直到他的信号低于检测水平。另一方面,在终止等离子体终止后,D分散可以达到几十秒的最大速度,并且该除气可以持续约10?分钟。这些引人注目的差异应与来自西等离子体面对部件的不同的保留和放栅有关,目前由主动冷却的浸渍W单位和惯性冷却的W涂层石墨构成。根据HE和D气体平衡的系统分析,讨论了D和D血浆D和H HE的原点的潜在机制,以及DEVERTOR击中点的D分散的宏观速率方程模型。

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