ITER L mode confinement database

Kaye, S. M.; Greenwald, M.; Stroth, U.; Kardaun, O.; Kus, A.; Schissel, D.P.; DeBoo, J. C.; Bracco, G.; Thomsen, K.; Cordey, J.G.; Miura, Y.; Matsuda, Toshiaki; Tamai, Hiroshi; Takizuda, T.; Hirayama, T.; Kikuchi, Hiromu; Naito, O.; Chudnovskij, A.; Ongena, J.; Hoang, G. T.

doi:10.1088/0029-5515/37/9/i10

Cited by 164 publications

(112 citation statements)

References 25 publications

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“…1, and the L-mode confinement scaling, Eq. 7 in [33]. For this purpose τ E and τ ei at the L-H transition are calculated, whereby the heating power is provided by the threshold scaling and n e,min is determined by τ E /τ ei = 9.…”

Section: Determination Of N Eminmentioning

confidence: 99%

Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition

et al. 2014

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Abstract.Experimental investigations carried out in the ASDEX Upgrade tokamak under various conditions demonstrate that the ion heat flux at the plasma edge plays a key role in the L-H transition physics, while the electron heat flux does not seem to play any role. This is due to the fact that the ion heat flux governs the radial electric field well induced by the main ions which is responsible for the turbulence stabilization causing the L-H transition. The experiments have been carried out in the low density branch of the power threshold where the electron and ion heat channels can be well separated. In plasmas heated by electron heating, the edge ion heat flux has been increased to reach the L-H transition by using separately three actuators: heating power, density and plasma current. In addition, the key role of the edge ion heating has been confirmed in experiments taking advantage of the direct ion heating provided by neutral beam injection. The role of the ion heat flux explains the non-monotonic density dependence of the L-H threshold power. Based on these results, a formula for the density of the threshold minimum has been developed, which also describes well the values found in tokamaks of various size. For ITER it predicts a value which is close to the density presently foreseen to enter the H-mode and indicates that operation at half field and current would benefit from a very significantly lower density minimum and correspondingly low threshold power.

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Section: Determination Of N Eminmentioning

confidence: 99%

Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition

et al. 2014

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“…2). These evaluations are based on a Bohm-gyroBohm formulation [13] for the electron thermal transport with specific coefficients calibrated so that the energy confinement time is around the value predicted by the ITER97-L mode scaling [14]. The RF heating compensates for a poorer fuel mixture and, as a result, steady state conditions of a burning, sawtoothing plasma can be maintained over the current flat top with values of the ignition factor K f ≡ P α /P L ∼ = 2/3, corresponding to a fusion gain Q ≡ P f us /P in 10.…”

Section: Rf Assisted Regimes and Burn Controlmentioning

confidence: 99%

Ignitor: physics and progress towards ignition

Bombarda¹,

Coppi²,

Airoldi³

et al. 2004

Braz. J. Phys.

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Thermonuclear ignition condition for deuterium-tritium plasmas can be achieved in compact, high magnetic field devices such as Ignitor. The main scientific goals, the underlying physics basis, and the most relevant engineering solutions of this experiment are described. Burning plasma conditions can be reached either with ohmic heating only or with small amount of auxiliary power in the form of ICRH waves, and this condition can be sustained for a time considerably longer than all the relevant plasma time scales. In the reference operating scenario, no transport barriers are present, and the resulting thermal loads on the plasma facing component are estimated to be rather modest, thanks to the high edge density and low edge temperature that ensure an effective intrinsic radiating mantle in elongated limiter configurations. Enhanced confinement regimes can also be obtained in configurations with double X-points near the first wall.

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“…For completeness, the performance with and without ECRH will also be compared with the ELM-free H-mode (ITER-93H) scaling, τ 93H , defined as [10] τ 93H = 0.036 · I 1 (2) The energy content expected on the basis of these scalings will be denoted by W RI and W 93H , and is given in figure 1 as well. As P ECRH /P tot 0.27/2.7 10% (in fact even less, since P drops during ECRH), equation (1) would predict a relative increase of stored energy (δW dia ) of typically 3%.…”

Section: Effect Of Ecrh On Global Confinementmentioning

confidence: 99%

Confinement and transport in EC heated RI-mode discharges in TEXTOR

Hogeweij¹,

Dumortier²,

Eester³

et al. 2004

Nucl. Fusion

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This paper reports on experiments in TEXTOR with electron cyclotron resonance heating (ECRH) of radiatively improved (RI) mode discharges. With ECRH the energy content of RI-mode discharges can be increased without the normally observed power degradation in confinement time. The experiments are described and the effects of ECRH on global confinement and local plasma parameters of RI-mode discharges are discussed; the favourable scaling of energy content is due to a zone of low electron thermal transport just outside the sawtooth inversion radius. Moreover, the heating effect of ECRH in the RI-mode is compared with the effect in L-mode; this comparison sheds some light on the physics of electron thermal transport in RI-mode discharges.

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ITER L mode confinement database

Cited by 164 publications

References 25 publications

Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition

Experimental evidence for the key role of the ion heat channel in the physics of the L–H transition

Ignitor: physics and progress towards ignition

Confinement and transport in EC heated RI-mode discharges in TEXTOR

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