Simulation of plasma transport in the linear plasma device MPS-LD by SOLPS-ITER

Zhang, Yanjie; Sang, Chaofeng; Sun, Changjiang; Wang, Min; Wang, Yue; Wang, Qi; Wang, Dezhen

doi:10.1016/j.nme.2022.101280

Cited by 4 publications

(4 citation statements)

References 23 publications

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“…Moreover, in the radial direction, N e , T e and T i gradually decrease toward the chamber wall, and the radial N e distributions are similar to those of the Magnum-PSI experiment [17]. Quantitative comparison between BOUT++ and SOLPS-ITER modeling of MPS-LD [34] is also carried out. The trends of the main parameters are in reasonable agreement.…”

Section: Preliminary Results and Verificationmentioning

confidence: 56%

Simulation of plasma transport in MPS-LD linear plasma device by using BOUT++

Wang¹,

Sang²,

Li³

et al. 2022

Plasma Phys. Control. Fusion

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A linear plasma device (LPD) module based on the 2D transport module under the BOUT++ framework is developed in this paper to simulate the plasma transport in the LPD. The LPD module includes three parts, i.e. magnetic field calculation, simulation mesh generation and plasma transport setup. Magnetic field is calculated by circular current loop using the location and current information of each coil. The mesh generation code can produce the simulation mesh for LPD employing the magnetic field. The plasma transport model is based on the reduced Braginskii equations, which consist of the continuity equation, momentum equation, and energy equation. The fluid neutral model is applied for the neutral particle simulation. Deuterium (D) and helium (He) ions and atoms can be simulated by the model. The first attempt to simulate the plasma transport in the new LPD called MPS-LD is presented using the developed model. The D plasma transport in the MPS-LD is simulated and benchmarked against the two-point model, showing the validation of the BOUT++ simulation. The effects of radial transport on the heat load to the target are studied, which illustrates significant impact of the radial diffusivities D_⊥ and χ_(⊥i,e)^c on the plasma. Moreover, the He impurity injection process during the discharge is studied with the emphasis on the plasma-impurity interactions. The simulation results show the He injection can reduce the plasma energy load to the target significantly, and the efficiency depends on the He source density and injection velocity. The present work provides an alternative and flexible simulation tool for the plasma transport in the LPD.

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Section: Preliminary Results and Verificationmentioning

confidence: 56%

Simulation of plasma transport in MPS-LD linear plasma device by using BOUT++

Wang¹,

Sang²,

Li³

et al. 2022

Plasma Phys. Control. Fusion

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“…However, the realization of high heating efficiency in medium and high density is a challenge. According to the SOLPS-ITER prediction modeling of MPS-LD, the plasma density at the edge of the plasma beam is higher than 10 18 m −3 [32], which will influence the heating efficiency according to previous section analysis. In figure 5, the density threshold is 5.5 × 10 14 m −3 .…”

Section: The Optimization Of Icrhmentioning

confidence: 97%

“…In order to realize the prediction of ion auxiliary heating in the MPS-LD device, based on the above analysis, the resonance magnetic field of 0.3 T is selected, and the magnetic field configuration is the real auxiliary heating configuration. Figure 11(a) shows the simulated hydrogen plasma density in MPS-LD by using SOLPS-ITER [32], and the location of ion auxiliary heating is labeled by the black dash line (z = −1.85 m). Figure 11(b) shows the corresponding radial density profiles, where the blue line is from the SOLPS-ITER When the resonance magnetic field is 0.3 T, the length of CDAL is about 0.06 m, and the ion parallel velocity equals approximately to the ion sound speed, i.e., when the temperature is 1.5 eV, v // ≈ 10 000 m s −1 .…”

Section: Simulation Prediction For Mps-ldmentioning

confidence: 99%

Simulation of ion cyclotron resonance heating by using particle-in-cell method in MPS-LD linear plasma device

Sun¹,

Sang²,

Wang³

et al. 2023

Plasma Phys. Control. Fusion

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The auxiliary heating of electrons and ions in linear plasma devices is necessary to achieve the boundary plasma relevant environment of tokamak, so that to investigate the boundary physics and plasma-material interactions. In this work, the simulation of ion cyclotron resonance heating (ICRH) in the linear plasma device MPS-LD is carried out by using a 3D particle-in-cell method, and the wave-ion interaction mechanism based on “beach-heating” technique in the ion heating region is investigated. A left-handed, circularly polarized wave along the magnetic field lines is used to represent the electromagnetic wave in the model, after the analysis of the cold plasma dispersion relation. The mechanism of ion heating by collisionless damping absorption is demonstrated and explained by using plasma current as the plasma response. The dependencies of the heating efficiency on the plasma density, magnetic field strength and magnetic field configuration are studied. The correlation between plasma density and magnetic field strength, which satisfies the heating efficiency, is found and it is in perfect agreement with the theoretical derivation. Finally, by using the designed parameters of MPS-LD provided by SOLPS-ITER, the prediction of ICRH is performed. The simulation result shows the ion temperature can be heated higher than 40 eV and it satisfies the requirement for SOL/divertor simulation experimentally in MPS-LD.

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“…Comparing with tokamak divertors, LPD has significant advantages in cost-effectiveness, convenience of disassembly and target plate replacement, facilitating the evaluation of experimental data, and ability to operate under high heat load conditions with extended pulse durations. Consequently, numerous institutions have devised restrictive LPDs including Magnum-PSI, [2][3][4] MAGPIE, [5,6] GyM, [7,8] Proto-MPEX, [9,10] and MPS-LPD, [11,12] with the purpose of studying the physics underlying PWI and advancing divertor target materials. According to the heat load estimate of the ITER divertor, the target should be capable of withstanding at least a heat flux of 10 MW • m −2 .…”

Section: Introduction and Device Descriptionmentioning

confidence: 99%

Numerical studies for plasmas of a linear plasma device HIT-PSI with geometry modified SOLPS-ITER

Wang 王,

Nie 聂,

Huang 黄

et al. 2024

Chinese Phys. B

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The HIT-PSI is a linear plasma device built for physically simulating the high heat flux environment of future reactor divertors to test/develop advanced target plate materials. In this study, the geometry modified SOLPS-ITER program is employed to examine the effects of the magnetic field strength and neutral pressure in the device on the heat flux experienced by the target plate of the HIT-PSI device. The findings of the numerical simulation indicate a positive correlation between the magnetic field strength and the heat flux density. Conversely, there is a negative correlation observed between the heat flux density and the neutral pressure. When the magnetic field strength at the axis exceeds 1 tesla and the neutral pressure falls below 10 Pa, the HIT-PSI has the capability to attain a heat flux of 10MV·m-2 at the target plate. The simulation results offer a valuable point of reference for subsequent experiments at HIT-PSI.

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Simulation of plasma transport in the linear plasma device MPS-LD by SOLPS-ITER

Cited by 4 publications

References 23 publications

Simulation of plasma transport in MPS-LD linear plasma device by using BOUT++

Simulation of plasma transport in MPS-LD linear plasma device by using BOUT++

Simulation of ion cyclotron resonance heating by using particle-in-cell method in MPS-LD linear plasma device

Numerical studies for plasmas of a linear plasma device HIT-PSI with geometry modified SOLPS-ITER

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