Dust-particle transport in tokamak edge plasmas

Pigarov, A. Yu.; Krasheninnikov, S. I.; Soboleva, T. K.; Rognlien, T. D.

doi:10.1063/1.2145157

Cited by 140 publications

(126 citation statements)

References 84 publications

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“…Our model includes a dust charging equation, the dust equation of motion, the dust heating equation and an equation for dust mass loss in the framework of the OML theory, and is similar to other dust transport models used in the literature [13][14][15][16][17]30].…”

Section: Discussionmentioning

confidence: 99%

“…For the orbital part of the ion drag force, we follow the model described in Refs. [13,14]. That is, for both negatively and positively charged grains, we have…”

Section: B Dust Equation Of Motionmentioning

confidence: 99%

“…For a negatively charged grain, the Coulomb logarithm log Λ is calculated as used in Ref. [13,14] to fit PIC simulation results obtained by Hutchinson [27]. For a positively charged grain, the Coulomb logarithm is given by [28] log Λ =…”

Section: B Dust Equation Of Motionmentioning

confidence: 99%

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Survivability of dust in tokamaks: Dust transport in the divertor sheath

Delzanno

Tang

2014

Physics of Plasmas

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The survivability of dust being transported in the magnetized sheath near the divertor plate of a tokamak and its impact on the desired balance of erosion and redeposition for a steady-state reactor are investigated. Two different divertor scenarios are considered. The first is characterized by an energy flux perpendicular to the plate q 0 1 MW/m 2 typical of current short-pulse tokamaks.The second has q 0 10 MW/m 2 and is relevant to long-pulse machines like ITER or DEMO.It is shown that micrometer dust particles can survive rather easily near the plates of a divertor plasma with q 0 1 MW/m 2 because thermal radiation provides adequate cooling for the dust particle. On the other hand, the survivability of micrometer dust particles near the divertor plates is drastically reduced when q 0 10 MW/m 2 . Micrometer dust particles redeposit their material non-locally, leading to a net poloidal mass migration across the divertor. Smaller particles (with radius ∼ 0.1 µm) cannot survive near the divertor and redeposit their material locally. Bigger particle (with radius ∼ 10 µm) can instead survive partially and move outside the divertor strike points, thus causing a net loss of divertor material to dust accumulation inside the chamber and some non-local redeposition. The implications of these results for ITER are discussed.

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Section: Discussionmentioning

confidence: 99%

“…For the orbital part of the ion drag force, we follow the model described in Refs. [13,14]. That is, for both negatively and positively charged grains, we have…”

Section: B Dust Equation Of Motionmentioning

confidence: 99%

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Survivability of dust in tokamaks: Dust transport in the divertor sheath

Delzanno

Tang

2014

Physics of Plasmas

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“…In this regime, the validity of the widely employed orbital motion limited (OML) framework [15][16][17][18] is strongly violated, leading to order-of-magnitude errors in the predictions of droplet charging and heating [19]. Moreover, the presence of highly charged ions from the impurity species, introduced by the disruption mitigation system, requires the inclusion of ion-induced emission processes, which are typically of little concern in standard scenarios with singly charged hydrogenic ions [20].…”

Section: Introductionmentioning

confidence: 99%

Survival and in-vessel redistribution of beryllium droplets after ITER disruptions

et al. 2018

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The motion and temperature evolution of beryllium droplets produced by first wall surface melting after ITER major disruptions and vertical displacement events mitigated during the current quench are simulated by the MIGRAINe dust dynamics code. These simulations employ an updated physical model which addresses droplet-plasma interaction in ITER-relevant regimes characterized by magnetized electron collection and thin-sheath ion collection, as well as electron emission processes induced by electron and high-Z ion impacts. The disruption scenarios have been implemented from DINA simulations of the time-evolving plasma parameters, while the droplet injection points are set to the first-wall locations expected to receive the highest thermal quench heat flux according to field line tracing studies. The droplet size, speed and ejection angle are varied within the range of currently available experimental and theoretical constraints, and the final quantities of interest are obtained by weighting single-trajectory output with different size and speed distributions. Detailed estimates of droplet solidification into dust grains and their subsequent deposition in the vessel are obtained. For representative distributions of the droplet injection parameters, the results indicate that at most a few percents of the beryllium mass initially injected is converted into solid dust, while the remaining mass either vaporizes or forms liquid splashes on the wall. Simulated in-vessel spatial distributions are also provided for the surviving dust, with the aim of providing guidance for planned dust diagnostic, retrieval and clean-up systems on ITER.

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“…After operation of plasma discharges, the collection and disposal of the radioactive dusts is one of key issues from the safety viewpoint. For these objectives the dynamics of the dust particle in fusion plasma is extensively studied [5][6][7]. In this paper we investigate dynamics of the dust particle in the SOL/divertor plasma of the HL-2A device [8], which is a divertor tokamak constructed in SWIP (Southwestern Institute of Physics) in Chengdu based on the original ASDEX main components [9,10].…”

Section: Introductionmentioning

confidence: 99%

Acceleration and Redeposition of a Dust Particle in SOL/Divertor Plasma of HL‐2A Tokamak

Tomita¹,

Kawamura²,

Pan³

et al. 2010

Contrib. Plasma Phys.

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Acceleration of a iron dust particle is studied in the SOL (Scrape-Off Layer)/divertor plasma of the HL-2A tokamak in Southwestern Institute of Physics, China, with a single-null configuration. In this study the simplest model of the dust dynamics is applied: spherical shape of a dust, ion drag force due to Coulomb scattering and drag force due to the plasma ion absorption as dominant forces, and spontaneous charging of a dust particle to the equilibrium charge. In the outer region near the plasma-facing wall the parallel plasma flow along the magnetic field pushes the dust particle to the divertor plates. It is clarified that the dust particle with a radius of 1mm from the top of the SOL/divertor region is accelerated up to around 100 m/s in a few hundreds milliseconds to the divertor plates. In our model even the small dust particle with 1nm size can overcome the sheath potential and redeposite on the divertor plate.

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Dust-particle transport in tokamak edge plasmas

Cited by 140 publications

References 84 publications

Survivability of dust in tokamaks: Dust transport in the divertor sheath

Survivability of dust in tokamaks: Dust transport in the divertor sheath

Survival and in-vessel redistribution of beryllium droplets after ITER disruptions

Acceleration and Redeposition of a Dust Particle in SOL/Divertor Plasma of HL‐2A Tokamak

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