Comparison of time dependent simulations with experiments in ion cyclotron heated plasmas

Eriksson, L.‐G.; Hellsten, T.; Willen, U.

doi:10.1088/0029-5515/33/7/i07

Cited by 236 publications

(300 citation statements)

References 29 publications

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“…It integrates, in a modular structure, a 1-D transport solver with general 2-D magnetic equilibria, self-consistently computed by the HELENA code [11], including several heat, particle and impurities transport models, as well as heat, particle, current and momentum sources. The source modules used in the simulations included here are the following: SINBAD [12] for NBI heating and current drive, PION [13] for ICRH, REMA [14] for EC ray tracing, with a linear estimate of the ECCD efficiency [15], Delphine [16] for LH ray tracing (including 2D Fokker-Planck evaluation of LHCD efficiency), and SPOT (an orbit following Monte Carlo code) for the alpha particles distribution function [17].…”

Section: Simulation Tools Used In Scenario Modelingmentioning

confidence: 99%

Simulation of the hybrid and steady state advanced operating modes in ITER

et al. 2007

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Abstract. Integrated simulations are done to establish a physics basis, in conjunction with present tokamak experiments, for the operating modes in ITER. Simulations of the hybrid mode are done using both fixed and free-boundary 1.5D transport evolution codes including CRONOS, ONETWO, TSC/TRANSP, TOPICS, and ASTRA. The hybrid operating mode is simulated using the GLF23 energy transport model. The injected powers are limited to the negative ion neutral beam (NBI), ion cyclotron (ICRF), and electron cyclotron (EC). Several plasma parameters and source parameters are specified for the hybrid cases to provide a comparison among the simulations. Simulations of the steady state operating mode are done with the same 1.5D transport evolution codes cited above. In these cases the energy transport model is more difficult to prescribe, so that energy confinement models will range from theory based to empirically based. The injected powers include the same sources for the hybrid with the possible addition of lower hybrid (LH). These simulations will be presented and compared with particular focus on code to code results when using the same energy transport model, and within the same code when using different energy transport models

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Section: Simulation Tools Used In Scenario Modelingmentioning

confidence: 99%

Simulation of the hybrid and steady state advanced operating modes in ITER

et al. 2007

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“…Nevertheless, due to the excellent localization of ECRH compared to ICRH and NBI, its contribution in the core is much higher. Figure 7(a) shows the power densities of ECRH, ICRH and NBI directly or indirectly absorbed by the electrons and the ions for discharge 89622, as calculated by the TORAY and PION codes, respectively [11,14]. The ICRH waves are for a very small part directly absorbed by the electrons and thermal deuterium ions; the major part is absorbed by the D beam ions and the H minority ions.…”

Section: Local Power Balance and Transportmentioning

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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“…Such ion heating is expected since the deuteron energy (E crit ) which gives equal collisional power transfer to the ions and electrons is 100 keV for an electron temperature of 7 keV [11]. Detailed theoretical calculations using the PION code [12] for discharge 43015 are given in references 8 and 13.…”

Section: Maximum Fusion Reactivitymentioning

confidence: 99%

Bulk ion heating with ICRH in JET DT plasmas

Start¹,

Jacquinot

Bergeaud

et al. 1999

Nucl. Fusion

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ABSTRACT.Reactor relevant ICRH scenarios have been assessed during D-T experiments on the JET tokamak using H-mode divertor discharges with ITER-like shapes and safety factors. Deuterium minority heating in tritium plasmas was demonstrated for the first time. For 9% deuterium, an ICRH power of 6 MW gave 1.66 MW of fusion power from reactions between suprathermal deuterons and thermal tritons. The Q-value of the steady state discharge reached 0.22 for the length of the RF flat top (2.7 s), corresponding to three plasma energy replacement times. The Doppler broadened neutron spectrum showed a deuteron energy of 125 keV which was optimum for fusion and close to the critical energy. Thus strong bulk ion heating was obtained at the same time as high fusion efficiency. Deuterium fractions around 20% produced the strongest ion heating together with a strong reduction of the suprathermal deuteron tail. The edge localised modes (ELMs) had low amplitude and high frequency and each ELM transported less plasma energy content

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Comparison of time dependent simulations with experiments in ion cyclotron heated plasmas

Cited by 236 publications

References 29 publications

Simulation of the hybrid and steady state advanced operating modes in ITER

Simulation of the hybrid and steady state advanced operating modes in ITER

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

Bulk ion heating with ICRH in JET DT plasmas

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