Digital storing and representation of spectral data of negative ions

Казаков, В. В.; Kazakov, V. G.; Zhumadilov, K. B.; Meshkov, O.; Yatsenko, A. S.

doi:10.1063/1.5083728

Cited by 2 publications

(2 citation statements)

References 8 publications

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“…However, for this three-ion heating scenario with a very low minority concentration, an ICRF antenna operating at low  k may be beneficial in increasing the coupling efficiency and maintaining an effective absorption. A similar result was reported in [43]. With optimized antenna design conditions for the CFETR, ).…”

Section: Analysis and Optimization Of Thesupporting

confidence: 83%

Numerical investigation of a new ICRF heating scenario in D-T plasma on CFETR

Song¹,

Yin²,

Yang³

et al. 2020

Phys. Scr.

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For a fusion device, plasma pre-heating is required before the self-sustaining burning-state reactions of deuterium (D) and tritium (T) commence. Plasma heating with waves in the ion-cyclotron range of frequencies (ICRF) is effective in tokamaks. A new three-ion ICRF heating scheme for plasmas in the Chinese Fusion Engineering Test Reactor (CFETR) that require an increase in the bulk ion temperature via heating the lithium impurities in the D–T plasmas, was studied numerically. Our simulations show that the radio-frequency wave power is strongly absorbed by very few 7Li ions with concentrations of 0.01%–0.2% in a suitable mixture of D–T plasmas, the enhanced minority ion heating is related to that the 7Li fundamental resonance layer is very close to the two mode conversion layers. In adjusting the mixtures over a wide range of composition, an oscillatory behaviour in the 7Li absorption efficiency arises because of interference. Moreover, from estimates of the 7Li ion tail energy, most of the tail energy of the minority ions is found to be transferred to background ions via collisions. Compared with the routine (3He)-D–T scheme, the ICRF power is absorbed more effectively by the 7Li ions in the (7Li)-D–T heating scenario, and after the Fokker–Planck equations were solved, a large fraction of bulk ion heating was evident in the (7Li)-D–T heating scenario. The new three-ion scenario may therefore be an attractive proposition for bulk ion heating during the activated phase of the reactor.

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Section: Analysis and Optimization Of Thesupporting

confidence: 83%

Numerical investigation of a new ICRF heating scenario in D-T plasma on CFETR

Song¹,

Yin²,

Yang³

et al. 2020

Phys. Scr.

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“…To deliver these objectives, ICRH was used in most JET-DTE2 and tritium plasmas to provide electron heating for central impurities chase out and discharges stationarity [5]. ICRH was also used for bulk heating of fuel ions and boost fusion power [6][7][8]. Specific experiments were performed to study the impact of isotopes on RF induced plasma wall interactions [9].…”

Section: Introductionmentioning

confidence: 99%

ICRH operations during the JET tritium and DTE2 campaigns

Jacquet,

Dumortier,

Lerche

et al. 2024

Nucl. Fusion

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The JET-ILW pure Tritium and Deuterium-Tritium (DTE2) experimental campaigns took place in 2021-2022. Tritium (T) and Deuterium-Tritium (D-T) operations present challenges not encountered in present day tokamaks [1]. This contribution focuses on Ion Cyclotron Resonance Heating (ICRH) operations in tritium and deuterium-tritium plasmas, starting with a summary of the program of improvements to the ICRH system which spanned a few years prior to these experiments. Procedures were implemented to address specific constraints from tritium and deuterium-tritium operations (tritium safety and reduced access to the RF generator area) and increase the system reliability and power availability during plasma pulses. Operation of the upgraded Real Time RF power control system that maximises the launched power while taking into account limitations from the system or antenna coupling is described. We also report on the result from dedicated pulses performed to assess the potential harmful impact of the 2nd harmonic tritium resonance in the plasma, close to the inner wall, when using the standard central hydrogen minority ICRH scheme. During DTE2, the ITER-Like Antenna (ILA) was not used because water leaked from an in-vessel capacitor into the vessel on day-2 of the experimental campaign. The lessons learnt from this incident are highlighted. Finally, the ICRH plant adjustments required to safely perform Ion Cyclotron Wall Cleaning discharges are described.

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Digital storing and representation of spectral data of negative ions

Cited by 2 publications

References 8 publications

Numerical investigation of a new ICRF heating scenario in D-T plasma on CFETR

Numerical investigation of a new ICRF heating scenario in D-T plasma on CFETR

ICRH operations during the JET tritium and DTE2 campaigns

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