Current Profile Reconstruction Using Motional Stark Effect Polarimeter Data on HL-2A Tokamak

Chen, W. J.; Yu, D.L.; Yan, L.W.; Yuan, B.S.; Liu, L.; Wei, Y. L.; Zhang, N.; He, Xiaoxue; Wu, Hao; Shi, Z.B.; Liu, Y.; Qi, Yang

doi:10.1080/15361055.2019.1629251

Cited by 2 publications

(3 citation statements)

References 27 publications

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“…First of all, the current filament method [28,30] is used to calculate the initial plasma flux ψ 0 in the computational domain. Specifically, the toroidal current density on the grid is regarded as a current filament and can be obtained approximately by equation (13) or (14).…”

Section: The Construction Scheme For the Free Boundary Conditionsmentioning

confidence: 99%

“…Current sources in each region are obtained via equations ( 12), ( 14)-( 16). D. Equations ( 7), (15), and (16) are simultaneously solved using the strongly implicit procedure method to update the magnetic flux ψ [28,34,35]. In the nth iteration, the iterative formula is…”

Section: Current Sources Located Outside the Computational Domainmentioning

confidence: 99%

“…In the 'limiter-type' free boundary, the plasma equilibrium is calculated with a tokamak coil field by imposing a fixed point where plasma interacts with the limiter. In the 'divertor-type' free boundary, the plasma-vacuum boundary flux value ψ, the position and the shape of plasma are unknown before calculation and defined by a set of tokamak coils and plasma current [24,28].…”

Section: Introductionmentioning

confidence: 99%

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Free-boundary plasma equilibria with toroidal plasma flows

Chen¹,

W.²,

Zhang³

et al. 2022

Plasma Sci. Technol.

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Magnetohydrodynamic equilibrium schemes with toroidal plasma flows and the scrape-off layer are developed for the 'divertor-type' and 'limiter-type' free boundaries in the tokamak cylindrical coordinator. With a toroidal plasma flow, the flux functions are considerably different under the isentropic and isothermal assumptions. The effects of the toroidal flow on the magnetic axis shift are investigated. In a high beta plasma, the magnetic shift due to the toroidal flow are almost the same for both the isentropic and isothermal cases, and are about 0.04a0 (a0 is the minor radius) for M0=0.2 (the toroidal Alfvѐn Mach number on the magnetic axis). In addition, the X-point is slightly shifted upward by 0.0125 a0. But the magnetic axis and the X-point shift due to the toroidal flow may be neglected because M0 is usually less than 0.05 in a real tokamak. The effects of the toroidal flow on the plasma parameters are also investigated. The high toroidal flow shifts the plasma outward due to the centrifugal effect. Temperature profiles are noticeable different because the plasma temperature is a flux function in the isothermal case.

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Section: The Construction Scheme For the Free Boundary Conditionsmentioning

confidence: 99%

Section: Current Sources Located Outside the Computational Domainmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Free-boundary plasma equilibria with toroidal plasma flows

Chen¹,

W.²,

Zhang³

et al. 2022

Plasma Sci. Technol.

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Poloidal magnetic field reconstruction by laser-driven ion-beam trace probe in spherical tokamak

ZHANG 张,

XU 徐,

XIAO 肖

et al. 2024

Plasma Sci. Technol.

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The poloidal magnetic field (B_p) plays a critical role in plasma equilibrium, confinement and transport of magnetic confinement devices. Multiple diagnostic methods are needed to complement each other to obtain a more accurate B_p profile. Recently, the laser-driven ion-beam trace probe (LITP) has been proposed as a promising tool for diagnosing B_p and radial electric field (E_r) profiles in tokamaks [Yang X Y et al 2014 Rev. Sci. Instrum. 85 11E429]. The spherical tokamak (ST) is a promising compact device with high plasma beta and naturally large elongation. However, when applying LITP to diagnosing B_p in STs, the larger B_p invalidates the linear reconstruction relationship for conventional tokamaks, necessitating the development of a nonlinear reconstruction principle tailored to STs. This novel approach employs an iterative reconstruction method based on Newton’s method to solve the nonlinear equation. Subsequently, a simulation model to reconstruct the B_p profile of STs is developed and the experimental setup of LITP is designed for EXL-50, a middle-sized ST. Simulation results of the reconstruction show that the relative errors of B_p reconstruction are mostly below 5%. Moreover, even with 5 mm measurement error on beam traces or 1 cm flux surface shape error, the average relative error of reconstruction remains below 15%, initially demonstrating the robustness of LITP in diagnosing B_p profiles in STs.

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Current Profile Reconstruction Using Motional Stark Effect Polarimeter Data on HL-2A Tokamak

Cited by 2 publications

References 27 publications

Free-boundary plasma equilibria with toroidal plasma flows

Free-boundary plasma equilibria with toroidal plasma flows

Poloidal magnetic field reconstruction by laser-driven ion-beam trace probe in spherical tokamak

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