Analysis and design of the Alfven wave antenna system for the SUNIST spherical tokamak

Tan, Yidong; Gao, Zhe; He, Yonghong

doi:10.1016/j.fusengdes.2008.12.051

Cited by 3 publications

(2 citation statements)

References 24 publications

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“…Although several results achieved on STs are specific to the spherical design, there are many features which are common between STs and conventional tokamaks [2,3]. Significant ST achievements have been made from mega-Ampere (MA) level devices like MAST [4] and NSTX [5,6], however contributions from the small ST devices cannot be ignored [7,8]. Small confinement devices have the advantage of flexibility in parameters and ease of access for the replacement/modification of components [9].…”

Section: Introductionmentioning

confidence: 99%

Optimization of magnetic field system for glass spherical tokamak GLAST-III

Ahmad

Naveed

et al. 2017

Phys. Scr.

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GLAST-III (Glass Spherical Tokamak) is a spherical tokamak with aspect ratio A = 2. The mapping of its magnetic system is performed to optimize the GLAST-III tokamak for plasma initiation using a Hall probe. Magnetic field from toroidal coils shows 1/R dependence which is typical with spherical tokamaks. Toroidal field (TF) coils can produce 875 Gauss field, an essential requirement for electron cyclotron resonance assisted discharge. The central solenoid (CS) of GLAST-III is an air core solenoid and requires compensation coils to reduce unnecessary magnetic flux inside the vessel region. The vertical component of magnetic field from the CS in the vacuum vessel region is reduced to 1.15 Gauss kA−1 with the help of a differential loop. The CS of GLAST can produce flux change up to 68 mVs. Theoretical and experimental results are compared for the current waveform of TF coils using a combination of fast and slow capacitor banks. Also the magnetic field produced by poloidal field (PF) coils is compared with theoretically predicted values. It is found that calculated results are in good agreement with experimental measurement. Consequently magnetic field measurements are validated. A tokamak discharge with 2 kA plasma current and pulse length 1 ms is successfully produced using different sets of coils.

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Section: Introductionmentioning

confidence: 99%

Optimization of magnetic field system for glass spherical tokamak GLAST-III

Ahmad

Naveed

et al. 2017

Phys. Scr.

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“…俘获电子在电流驱动中的效应仍需进一步的理论和实验研究. 理论研究需要考虑长时间尺度下多物理过程的竞争和影响; 而在实验研究则可以考虑在长脉冲准稳态放电的超导托卡马克以及具有更高俘获电子比例的球形托卡马克上开展 [17] . 获得高效率的非对称直接驱动的另一个极限是高相速度波.…”

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Radio-frequency current drive and flow drive in magnetic confinement fusion plasma

Gao¹

2014

Chin. Sci. Bull.

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Radio-frequency (rf) waves can penetrate fusion plasmas and deposit energy and momentum through collisionless mechanisms, resulting in plasma heating and, in some cases, current drive and flow drive. The advantage of this noninductive current drive is that a tokamak-type fusion reactor can be operated at a steady state. Meanwhile, an appropriate profile of plasma current and a significant plasma flow are important in stabilizing magnetohydrodynamics instabilities and realizing and sustaining high-performance confinement regimes. Therefore, rf current drive and flow drive are important in research on the physics of magnetic confinement fusion plasma. This paper presents the elementary physics of wave-particle interactions in plasmas, reviews the present status and challenges of research on rf current drive and flow drive, and suggests possible research strategies. Several problems are highlighted. These include the intrinsic relation of resonant absorption to the reduction of rf current drive efficiency in high-density plasmas; the existence/feasibility of a nonresonant drive scheme; the possibility of increasing the drive efficiency within the resonant mechanism; the direct and indirect effects of rf waves in flow drive, especially the generalized ponderomotive force generated by rf waves; and nonlinear processes during the coupling and propagation of waves, such as parametric decay instabilities, and their possible effects on current drive and flow drive.

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Determination of limiter design and material composition of MT-II spherical tokamak

Khan¹,

Abdullah²,

Ali³

et al. 2022

Kerntechnik

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MT-II is a spherical tokamak with a major radius of 0.15 m and a minor radius of 0.09 m, currently under development at the Pakistan Tokamak Plasma Research Institute. It is designed with a higher elongation of 2.67. This paper presents the design and material analysis of the limiter configuration for the MT-II tokamak, which is being carried out in two phases. In the first phase, theoretical studies and calculations are performed to estimate the plasma edge temperature, density, particle velocity, input power, heat flux, heat load and surface temperature on the limiter tile. In the second phase, computational techniques are applied to analyses the material properties, the maximum/minimum surface temperature rise (∆T °C) at stable heat load and power deposition based on theoretical calculations that will help optimize the design parameters of the limiter. The type of material and the surface temperature of the limiter as well as the general design parameters of MT-II are included in the proposed poloidal limiter. The results suggest that crystalline vein graphite is a suitable candidate for the proposed poloidal limiter. A combination of mechanical and electrical feedthrough techniques are used to improve the performance of the limiter. The proposed limiter is able to meet the requirements of MT-II.

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Analysis and design of the Alfven wave antenna system for the SUNIST spherical tokamak

Cited by 3 publications

References 24 publications

Optimization of magnetic field system for glass spherical tokamak GLAST-III

Optimization of magnetic field system for glass spherical tokamak GLAST-III

Radio-frequency current drive and flow drive in magnetic confinement fusion plasma

Determination of limiter design and material composition of MT-II spherical tokamak

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