Predictive study of high performance scenarios in HL-2A

Gao, Qian; Budny, R.; Li, F.; Zhang, J.

doi:10.1088/0029-5515/43/9/324

Cited by 7 publications

(5 citation statements)

References 29 publications

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“…Here, β N = β T /(I /aB T ) is the normalized toroidal β, β T = 2µ 0 p /B 2 T , I is the plasma current in MA, a is the plasma minor radius in m, B T is the toroidal magnetic field in Tesla; H 89 is the confinement enhanced factor relative to ITER89-P scaling [9]. The DB plasma is then a promising regime for high performance steady operation [3,4,10,11]. However, the transport barriers lead to large pressure gradient P and large bootstrap current density J BS , which often drive MHD instabilities.…”

Section: Introductionmentioning

confidence: 99%

Ideal MHD stability of double transport barrier plasmas in DIII-D

Wang

Lao

et al. 2008

Nucl. Fusion

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The ideal MHD stability for double transport barrier (DTB or DB) plasmas with varying edge and internal barrier width and height was investigated, using the ideal MHD stability code GATO. A moderate ratio of edge transport barriers (ETB) height to internal transport barriers (ITBs) height is found to be beneficial to MHD stability and the β N is limited by global low n instabilities. For moderate ITB width DB plasmas, if the ETB is weak, the stability is limited by n = 1 (n is the toroidal mode number) global mode; whereas if the ETB is strong it is limited by intermediate-n edge peeling-ballooning modes. Broadening the ITB can improve stability if the ITB half width w i 0.3. For very broad ITB width plasmas the stability is limited by stability to a low n (n > 1) global mode.

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Section: Introductionmentioning

confidence: 99%

Ideal MHD stability of double transport barrier plasmas in DIII-D

Wang

Lao

et al. 2008

Nucl. Fusion

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“…where n ||0 and R 0 refer to the toroidal mode number n launched at the antenna R 0 , q2 = q cyl /εx (q cyl is the cylindrical safety factor, ε = a/R) is a magnetic geometry factor, and ε ⊥ = 1 + ω 2 pe /ω 2 ce -Σ j ω 2 pi,j /ω 2 (ω ce , ω pi and ω pe are the electron gyro-frequency, ion and electron plasma frequencies, respectively) [27] . So the safety factor and density can affect the absorption of the LHW power.…”

Section: Discussionmentioning

confidence: 99%

Sawtooth Control Experiments on HT-7 and EAST Tokamak

Liu¹,

Gao²,

Jie³

et al. 2012

Plasma Sci. Technol.

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Sawtooth control experiments were performed on HT-7 with a limiter configuration and on the Experimental Advanced Superconducting Tokamak (EAST) with a double null configuration. The sawtooth period can be modified by lower hybrid wave (LHW) and ion cyclotron resonance frequency (ICRF). Different sawtooth behavior was observed with the same plasma density, LHW power but different plasma currents on HT-7. There was a dwell time between LHW added and the sawtooth stabilization on HT-7 while the sawtooth stabilization immediately happened when LHW power was injected on EAST. The possible mechanism of the sawtooth control is discussed in this paper. All the experimental results have proved that power deposition of the radio frequency (RF) should be the key factor for sawtooth control.

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“…5a). The analysis of wave deposition region in the ( , n // ) phase space shows that constraint imposed by the wave propagation condition limits the maximum allowed n // -upshift [17]. Taking into account the Landau damping condition, it is shown that LH power deposits off-axis.…”

Section: Lower Hybrid Wave Heating and Eitbmentioning

confidence: 99%

Modelling of Profile Control with Lower Hybrid Wave Injection in the HL-2A Single-Null Divertor Plasma

Gao

Wang²,

Yuan³

2009

TOPPJ

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Separatrix of the single-null diverted plasma produced in the HL-2A tokamak is determined by a fast algorithm for identifying plasma boundary. Higher power LH wave (1.5MW) is injected into the diverted plasma with a slightly asymmetric spectrum. Plasma heating by electron Landau interaction results in operation scenarios of preferentially dominant electron heating. Current profile control under the dominant electron heating condition is investigated with numerical simulation. Due to the off-axis driven current, an RS q-profile is formed, and an enhanced confinement regime with steep electron temperature gradient is produced. The clear decrease of the electron thermal conductivity in the vicinity of the shear reversal shows that an electron-ITB is developed. When higher LH power injects into the target plasma that is heated by neutral beam injection, the ion temperature has a large increment in addition to the high increase of electron temperature. The temperature profiles indicate that an enhanced core confinement is established with both ion-ITB and electron-ITB developed.

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Predictive study of high performance scenarios in HL-2A

Cited by 7 publications

References 29 publications

Ideal MHD stability of double transport barrier plasmas in DIII-D

Ideal MHD stability of double transport barrier plasmas in DIII-D

Sawtooth Control Experiments on HT-7 and EAST Tokamak

Modelling of Profile Control with Lower Hybrid Wave Injection in the HL-2A Single-Null Divertor Plasma

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