Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Liang, Lizhen; Hu, Chundong; Xie, Yuanlai; Guo, Qiang; Xie, Yahong

doi:10.1088/1009-0630/13/4/22

Cited by 12 publications

(4 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The prediction and expansion of divertor power footprint widths are the main tasks for SOL physics research. Experimental studies on the SOL heat flux width have been carried out on most of the current tokamaks [5][6][7][8][9][10][11][12][13][14][15]. The basic finding is the negative dependence of λ q on I p [11][12][13][14][15], which is consistent with the heuristic drift-based model proposed by Goldston [16], indicating that λ q would narrow to about 1 mm when extrapolated to ITER [11].…”

Section: Introductionsupporting

confidence: 71%

Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene

Deng

Liu

Wang

2017

Plasma Sci. Technol.

View full text Add to dashboard Cite

The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak (EAST) L-mode and ELM-free H-mode plasmas. The divertor power footprint widths, which consist of the scrape-off layer (SOL) width λ q and heat spreading S, are important physical parameters for edge plasmas. In this work, a plasma current scan is implemented in the simulation to obtain the dependence of the divertor power footprint width on the plasma current I p . Strong inverse scaling of the SOL width with I p has been achieved for both L-mode and H-mode plasmas in the forms of -H mode p 0.872 In addition, studies on divertor peak heat load and the magnetic flux expansion factor show that both of them are proportional to plasma current. The simulation work here can act as a way to explore the power footprint widths of future tokamak fusion devices such as ITER and the China Fusion Engineering Test Reactor (CFETR).

show abstract

Section: Introductionsupporting

confidence: 71%

Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene

Deng

Liu

Wang

2017

Plasma Sci. Technol.

View full text Add to dashboard Cite

show abstract

“…As mentioned in section-2, the grid set in the ROBIN device is segmented and tilted with an angle θ = 0.873 • with the vertical(y-axis) towards the beam(z-axis) axis. Individual grid segments are treated as tilted axes with respect to the lab frame and center of the GG as the origin [11]. The transformed axes for both top and bottom grid half were obtained and used as inputs for the equation-2.…”

Section: Beam Modelmentioning

confidence: 99%

Visible camera-based diagnostic to study negative ion beam profiles in ROBIN ion source

Dash,

Bandyopadhyay,

Pandya

et al. 2024

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

Ensuring ion beam quality is of prime importance concerning the design of large-size neutral beam injectors(NBIs). Homogeneity, divergence, and beam energy are three crucial parameters defining beam quality. ROBIN(RF-Operated Beam source in India for Negative ions) source is one such prototype for extracting H− ion beam from hydrogen plasma. The extracted beam interacts with background neutrals and emits photons. These emissions are proportional to current density and the visible range emissions are used to characterize the beam using CCD cameras. The observed vertical emission profiles depict Gaussian-type asymmetric wings with a tilted flat-top that suggest non-uniform beam groups from the two grid segments. Divergence data extracted from the camera decreases with the acceleration voltage sweep. A strong correlation of the camera divergence data with calorimeter measurements was observed. A numerical beam model is in development to provide more insight into this correlation and pave the way to study beam group interaction.

show abstract

“…Then, using the random number, the location of one simulation particle is determined. Through this method, the distribution of simulated particle will meet the beam intensity distribution formula [16]. The validity of the simulation is determined by judging the simulated particle within the beam cross section.…”

Section: D Dsmc Modelingmentioning

confidence: 99%

Ion beam optics analysis and beam transmission simulation in the reflection magnet of the EAST NBI system

Liang

Wei

2014

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

Detailed trajectories of the residual ion passing through a reflection magnet, which is installed in the Experimental Advanced Superconducting Tokamak (EAST) neutral beam injector (NBI) system to remove the residual ion from the beam path, are reported. Monte Carlo simulation has been performed to obtain estimations of the beam density on the high heat flux elements of reflection magnet. On magnet pole shielding, there are three high beam power density regions, resulting from beam line focus and corresponding to the full energy, half energy and third energy. These high heat flux regions will bring a serious challenge for steady-state operation. The simulation result indicates that the re-ionization loss is about 2.43% and the magnet pole shielding encounters a problem of beam line focus, which should be taken seriously during the steady-state operation.

show abstract

Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Cited by 12 publications

References 8 publications

Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene

Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene

Visible camera-based diagnostic to study negative ion beam profiles in ROBIN ion source

Ion beam optics analysis and beam transmission simulation in the reflection magnet of the EAST NBI system

Contact Info

Product

Resources

About