2013
DOI: 10.1088/1009-0630/15/3/08
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Observation of Impurity Accumulation After Hydrogen Multi-Pellet Injection in Large Helical Device

Abstract: Impurity accumulation is studied for neutral beam-heated discharges after hydrogen multi-pellet injection in Large Helical Device (LHD). Iron density profiles are derived from radial profiles of EUV line emissions of FeXV-XXIV with the help of the collisional-radiative model. A peaked density profile of Fe 23+ is simulated by using one-dimensional impurity transport code. The result indicates a large inward velocity of −6 m/s at the impurity accumulation phase. However, the discharge is not entirely affected b… Show more

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Cited by 4 publications
(4 citation statements)
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“…Since the impurity accumulation itself is not the main subject of this paper, we do not describe the details here. The details of the impurity accumulation can be found in [55].…”
Section: Nb-heated Discharges With Iron Impurity Buildupmentioning
confidence: 99%
“…Since the impurity accumulation itself is not the main subject of this paper, we do not describe the details here. The details of the impurity accumulation can be found in [55].…”
Section: Nb-heated Discharges With Iron Impurity Buildupmentioning
confidence: 99%
“…5) However, the iron emission from lower ionization stages obviously increases after hydrogen multi-pellet injection because the emission location moves from the plasma edge to the plasma core owing to a sudden temperature decrease. 26,27) To examine the temporal resolution of the upgraded EUV spectrometer system, the temporal behavior of FeXV (284.147 Å) vertical profiles is observed in n-NBI discharges with p-NBI modulation and hydrogen multi-pellet injection. The sampling time of the CCD is set to 50 ms.…”
Section: Temporal Evolution Of Impurity Vertical Profilesmentioning
confidence: 99%
“…[12] Experimental impurity transport investigations have been performed in many magnetic confinement devices and most of the impurity transport studies have been carried out using the spatial profiles of absolute intensities of spectral emissions from spectroscopic measurement and comparison with an impurity transport code to determine the transport coefficients. [13][14][15][16][17][18] A future reactor will use high-Z plasma facing components (PFCs) such as tungsten in order to provide low erosion, sputtering yield and tritium retention. Since 2012, the first wall material of EAST has been mostly changed into molybdenum, which makes molybdenum as the most commonly seen metal impurity.…”
Section: Introductionmentioning
confidence: 99%