The influence of the radial particle transport on the divertor plasma detachment

Hoshino, Kazuo; Shimizu, K.; Takizuka, T.; Asakura, N.; Nakano, T.

doi:10.1016/j.jnucmat.2014.11.133

Cited by 14 publications

(19 citation statements)

References 15 publications

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“…In addition to the volume recombination, the radial plasma diffusion is a candidate in reducing the particle flux to the divertor plates [5]. Moreover, from the kinetic simulation results, it was predicted that supersonic flows, which could promote the smooth transition from attached to detached regime, could be driven by the radial plasma diffusion [7].…”

Section: Summary and Discussionmentioning

confidence: 99%

“…Detachment of divertor plasma is considered to be essential to reduce particle and heat fluxes to the divertor plates drastically. The physics of them, however, is still not fully been understood and the control method of them have not satisfactorily been developed so far although it has been investigated experimentally [2,3] and numerically [4,5].…”

Section: Introductionmentioning

confidence: 99%

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Simulation Study of Detached Plasmas by Using One‐Dimensional SOL‐Divertor Fluid Code with Virtual Divertor Model

Togo

Takizuka

Nakamura

et al. 2016

Contrib. Plasma Phys.

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The detached plasmas due to the volume recombination are studied by using one-dimensional (1D) scrape-offlayer-divertor (SOL-DIV) plasma fluid code with virtual divertor (VD) model. By introducing the anisotropic ion temperature, the parallel momentum transport equation becomes the first-order differential and the Mach number at the sheath entrance is determined self-consistently by the upstream condition. The total particle flux at the divertor plates and the flux amplification factors are shown as functions of the plasma density at the stagnation point and the dependence of these parameters on the heat flux from the core plasma, radial width of the flux tube in the divetor region and the strength of the impurity radiation is investigated.

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Section: Summary and Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Simulation Study of Detached Plasmas by Using One‐Dimensional SOL‐Divertor Fluid Code with Virtual Divertor Model

Togo

Takizuka

Nakamura

et al. 2016

Contrib. Plasma Phys.

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“…The number of numerical cells was setto 10000. Boundary conditions (described in section 2.2) were adopted except for the upstream, and the upstream boundary condition was provided based on the experimental value [9].…”

Section: Calculation Scheme and Flowmentioning

confidence: 99%

“…Various SOL/divertor codes have been developed for the design and prediction of fusion devices, including SOLPS [1][2][3], SONIC [4,5], EDGE2D [6], UEDGE [7], and EMC3-Eirene [8]. Although these codes have been very successful, the simulation of the JT-60U experimentusing the SONIC code has overestimated the ion flux at the strike pointby a factor of two or more with respect to the experimental value [9]. Some other important quantities have also not been reproduced correctly, from a quantitative point of view.…”

Section: Introductionmentioning

confidence: 99%

Effect of Large-Angle Scattering between Ions and Neutral Particles on the Density Profile at the Divertor Plate

Umezaki

Matsuura

2021

Plasma and Fusion Research

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The better radial transport modelling of the SOL/divertor plasmas is required to obtain quantitative agreements between experimental values and simulation results towards the proper SOL/divertor plasma prediction of the future magnetic fusion devices. Various SOL/divertor codes (e.g. SONIC, SOLPS-ITER, EDGE2D, UEDGE, EMC3-Eirene, etc.) have been developed and applied to the interpretative simulations of the present fusion devices. Above codes treats the radial transport as a diffusion model and there exists uncertainty to decide the value of the diffusion coefficients. The simulation by the SONIC has resulted in a few times larger ion flux towards the divertor plate than the experimental value observed in JT-60U possibly due to such an uncertainty of the diffusion process. To achieve the quantitative agreement between the experiments and the simulation results is indispensable to predict SOL/divertor plasma parameters of the future fusion devices. Here, radial transport was simulated by considering large-angle elastic scattering between ions and neutral particles and by applying the probability distribution function to fluid equations in the divertor plasma. It was found that the density peak and ion flux are reduced by about half.

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“…Recently, the SONIC has been improved to include: (1) contribution from the impurities to the electron density, (2) the ion heat flux limiter, (3) smoothing source terms near the target to reduce the Monte-Carlo noise/perturbation, and (4) time averaging of the impurity Monte-Carlo result to reduce the large oscillation. The improved SONIC code can qualitatively reproduce the characteristics of the JT-60U detached divertor plasma [11].…”

Section: Numerical Modelmentioning

confidence: 99%

Progress of Divertor Study on DEMO Design

Hoshino

Asakura

Tokunaga

et al. 2017

Plasma and Fusion Research

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Recent progress of the physics and engineering design study for the 8 m-sized DEMO is reported. Parametric study for the divertor of the compact DEMO (a machine size ∼ 5.5 m) by using the SONIC code shows that the target heat load less than 10 MW/m 2 around the fusion power of ∼1.5 GW and the impurity radiation fraction of more than 80%. In the 8 m sized DEMO with these parameters, the partial detachment is obtained at the outer divertor, even in the low SOL density, due to the large impurity radiation in the SOL and divertor region. The SONIC simulation shows the peak of the target heat load is 7 MW/m 2 . However, the peak of the ion temperature at the target is considerably high, which causes significant erosion of the target. The divertor power handling and decrease in the ion temperature have to be proceeded by the scenario development of the divertor plasma operation as well as the core plasma design and the engineering design. In the engineering study side, the tungsten monoblock target with the water cooling and the Cu-alloy cooling tube is designed. The MCNP-5 neutronics analysis shows applicability of the Cu-alloy cooling tube for the divertor unit on the high heat flux region. Also the divertor cassette with a heat removability of peak heat load of 10 MW/m 2 is studied. The heat transport analysis shows the maximum temperature of 1021• C at the tungsten surface and 331• C at the Cu-alloy pipe, which are acceptable level for mechanical toughness and thermal fatigue.

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The influence of the radial particle transport on the divertor plasma detachment

Cited by 14 publications

References 15 publications

Simulation Study of Detached Plasmas by Using One‐Dimensional SOL‐Divertor Fluid Code with Virtual Divertor Model

Simulation Study of Detached Plasmas by Using One‐Dimensional SOL‐Divertor Fluid Code with Virtual Divertor Model

Effect of Large-Angle Scattering between Ions and Neutral Particles on the Density Profile at the Divertor Plate

Progress of Divertor Study on DEMO Design

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