ICRH physics and technology achievements in JET-ILW

Jacquet, Philippe; Eester, D. Van; Lerche, E.; Bobkov, V.; Blackman, T.; Colas, L.; Challis, C.; Czarnecka, A.; Dumortier, P.; Frigione, D.; Durodié, F.; Garzotti, L.; Goniche, M.; Graves, J. P.; Kazakov, Ye. O.; Kirov, K.; Krawczyk, N.; Křivská, A.; Mantsinen, M.; Monakhov, I.; Nunes, I.; Ongena, J.; Reinke, M.L.; Rimini, F.; Zhang, W.; Contributors, Jet

doi:10.1051/epjconf/201715702004

Cited by 5 publications

(5 citation statements)

References 19 publications

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“…The scenarios of figures 1 and 2(a) are also identified by the three black small circles on this figure. 3 He minority is a more efficient scheme for ion heating depending on the 3 He concentration used in the plasma [57]. Reproduced from [57].…”

Section: Fusion Predictions For D-t Scenariosmentioning

confidence: 99%

“…The N = 1 H/N = 2 D ICRH scenario has been shown to maximize central electron heating, thus providing peaked temper ature profiles (figure 6, top) and increased turbulent transport to prevent W accumulation [54][55][56]. ICRH coupling is aided by dedicated gas injection in the main chamber magnetically connected with the ICRH antennas [57]. Although ICRH is the main tool used to prevent W accumulation in the centre of JET plasmas, application of ICRH can lead to an overall increase of the plasma impurity content, in particular in JET-ITER-like wall (ILW), tungsten (W) and nickel (Ni).…”

Section: The Role Of Icrh Power In the Development Of The D-t Scenariomentioning

confidence: 99%

“…Comparison the effect on plasma electron and ion temperature of the different ICRH schemes N = 1 H minority and N = 1 3 He minority and combined: T e (a) and T i (b) from charge exchange spectroscopy. Note that the N = 13 He minority is a more efficient scheme for ion heating depending on the3 He concentration used in the plasma[57]. Reproduced from[57].…”

mentioning

confidence: 99%

“…Note that the N = 13 He minority is a more efficient scheme for ion heating depending on the3 He concentration used in the plasma[57]. Reproduced from[57]. CC BY 4.0.…”

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Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall

et al. 2019

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We present an ultrafast neural network (NN) model, QLKNN, which predicts core tokamak transport heat and particle fluxes. QLKNN is a surrogate model based on a database of 300 million flux calculations of the quasilinear gyrokinetic transport model QuaLiKiz. The database covers a wide range of realistic tokamak core parameters. Physical features such as the existence of a critical gradient for the onset of turbulent transport were integrated into the neural network training methodology. We have coupled QLKNN to the tokamak modelling framework JINTRAC and rapid control-oriented tokamak transport solver RAPTOR. The coupled frameworks are demonstrated and validated through application to three JET shots covering a representative spread of H-mode operating space, predicting turbulent transport of energy and particles in the plasma core. JINTRAC-QLKNN and RAPTOR-QLKNN are able to accurately reproduce JINTRAC-QuaLiKiz T i,e and n e profiles, but 3 to 5 orders of magnitude faster. Simulations which take hours are reduced down to only a few tens of seconds. The discrepancy in the final source-driven predicted profiles between QLKNN and QuaLiKiz is on the order 1%-15%. Also the dynamic behaviour was well captured by QLKNN, with differences of only 4%-10% compared to JINTRAC-QuaLiKiz observed at mid-radius, for a study of density buildup following the L-H transition. Deployment of neural network surrogate models in multi-physics integrated tokamak modelling is a promising route towards enabling accurate and fast tokamak scenario optimization, Uncertainty Quantification, and control applications.

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Section: Fusion Predictions For D-t Scenariosmentioning

confidence: 99%

Section: The Role Of Icrh Power In the Development Of The D-t Scenariomentioning

confidence: 99%

mentioning

confidence: 99%

“…Note that the N = 13 He minority is a more efficient scheme for ion heating depending on the3 He concentration used in the plasma[57]. Reproduced from[57]. CC BY 4.0.…”

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Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall

et al. 2019

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“…The ICRF heating scenarios include: (1) the minority ion fundamental resonance heating scenario, in which the wave power is absorbed by the minority ions when both their cyclotron frequency and wave frequency match, and then the minority ions transfer energy to the background ions and electrons through collisions; (2) the majority ion harmonic resonance heating scenario; and (3) the electron heating scenario. The FW can directly damp on the electrons via electron Landau damping (ELD) and the transit-time magnetic pumping (TTMP) [6][7][8][9][10][11][12]. An ICRF heating system for the CFETR is planned for instalment.…”

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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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Numerical investigation of a minority heating scenario in three-ion components plasma on EAST

et al. 2020

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Heating with the wave in the ion cyclotron range of frequencies (ICRF) has been used in the development of high-performance H-mode operations in EAST. A different ion cyclotron resonance heating scenario in three-ion component plasma with real experimental parameters on EAST was investigated using a numerical tool. Excellent radio frequency wave absorption was found with an extremely low 3He concentration (0.1%–0.4%) in D-H-(3He) plasma, by adjusting the plasma composition appropriately in our simulation. In this case, the 3He fundamental resonance layer is located between the two ion–ion hybrid resonance-cutoff pairs in close proximity, and therefore E+ of the wave was considerably enhanced near the 3He fundamental resonance layer. The minority 3He tail was estimated to be superenergetic (∼1 MeV) because of the high power carried by each resonant 3He ion. The potential of the three-ion ICRF heating means on EAST was shown, and the scenarios investigated are particularly promising for fast particle generation schemes.

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ICRH physics and technology achievements in JET-ILW

Cited by 5 publications

References 19 publications

Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall

Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall

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

Numerical investigation of a minority heating scenario in three-ion components plasma on EAST

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