Three-dimensional simulation of neutral transport in gases and weakly ionized plasmas

Varshavchik, L. A.; Babinov, N.A.; Zatylkin, P. A.; Chironova, A. A.; Lyullin, Z. G.; Chernakov, Al.P.; Dmitriev, A. M.; Bukreev, I.M.; Mukhin, E.; Razdobarin, A. G.; Samsonov, Dmitry; Senitchenkov, V.A.; Tolstyakov, S.Yu.; Serenkov, I. T.; Сахаров, В. И.

doi:10.1088/1361-6587/abca7e

Cited by 4 publications

(5 citation statements)

References 29 publications

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Section: Sputtered Particle Transport and Parasitic Re-depositionmentioning

confidence: 99%

“…In addition to the experimental efforts described above (Sections 3.1 and 3.2), a Monte Carlo code (KITe) [20] is being developed to model sputtered particle transport in rarified and weakly-ionized gases relevant to ITER mirror cleaning experimental conditions. It is validated against experiments at the Ioffe Institute [20] and at Magnum-PSI [21]. The main code features are: a) possibility to import complex 3D geometry from CAD-files; b) results (plasma density, energy distribution functions) from 3D plasma simulation of RF discharges used as input; c) quantitative description of particle collisions in the background gas with given temperature using realistic interaction potential; d) accounting for particle-surface interaction based on BCA calculations with energy and angular distributions; e) computational performance allowing 10 7 -10 9 test particles to be traced in each simulation.…”

Section: Sputtered Particle Transport and Parasitic Re-depositionmentioning

confidence: 99%

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RF discharge mirror cleaning system development for ITER diagnostics

Shigin

Babinov

Temmerman

et al. 2021

Fusion Engineering and Design

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Section: Sputtered Particle Transport and Parasitic Re-depositionmentioning

confidence: 99%

Section: Sputtered Particle Transport and Parasitic Re-depositionmentioning

confidence: 99%

RF discharge mirror cleaning system development for ITER diagnostics

Shigin

Babinov

Temmerman

et al. 2021

Fusion Engineering and Design

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“…The particle transport was simulated with 3D Monte Carlo code KITe [8]. The code is capable of transport simulation of neutral particles in weakly ionized plasmas and neutral gases.…”

Section: Simulation Approachmentioning

confidence: 99%

“…The code is capable of transport simulation of neutral particles in weakly ionized plasmas and neutral gases. The main advantage of KITe is the ability to use complex approaches to calculating elastic collisions of particles in the energy range from 0.03 eV to ∼100 eV and the high performance provided by pre-calculated scattering data stored in a database [8]. This is very important because the velocity dependence of the cross-section (both total and differential) in the range of interest is complex and must be taken into account.…”

Section: Simulation Approachmentioning

confidence: 99%

Three-dimensional modeling of sputtered materials transport in diagnostic ducts of fusion devices

Babinov¹,

Razdobarin²,

Bukreev³

et al. 2022

Nucl. Fusion

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Migration of plasma erosion products in plasma facilities is studied experimentally and numerically within the framework of modelling transport of plasma-facing materials in the diagnostic ducts of fusion devices. Material transport simulation is discussed for two cases of low and high background neutral gas pressures. Monte Carlo software KITe was used to simulate transport at a neutral gas background pressure 0.1 – 0.5 Pa – typical during steady-state tokamak operation and during pressure pulses caused by edge localized modes (ELMs). The simulation approach was implemented to describe experiments at the MAGNUM-PSI facility. Fluid dynamic code FLUENT is used to simulate transport during pressure surges as high as 1000 Pa, which can occur in case of severe disruptions in tokamak plasma discharges, such as vertical displacement events (VDE) or accidental events. The hydrodynamic approach was verified in simulation of target sputtering in the QSPA plasma gun facility.

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“…Even at a low ion energy of 20-30 eV, they observed a sputtering and re-deposition of the stainless steel (SS) walls on the second mirror in the mock up. In a recent publication, Varshavchik et al modelled the transport of the sputtered Be particles in weakly ionised helium gas in mirror cleaning experimental conditions relevant to ITER [23]. The simulations showed that transport and re-deposition of the sputtered atoms significantly affect the cleaning efficiency and homogeneity at a few Pa of gas pressure.…”

Section: Introductionmentioning

confidence: 99%

Study of wall re-deposition on DC-grounded ITER-relevant mirrors with RF plasma in a first mirror unit

et al. 2021

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In ITER, several first mirrors (FMs) are expected to be DC-grounded with the water cooling lines being implemented as a quarter wavelength (λ/4) RF-filter. DC-grounding of the FMs can significantly increase the plasma potential V p, which could trigger an increased wall sputtering and associated re-deposition on the FMs during plasma cleaning. To understand the scope of this impact, helium discharges were excited with DC-grounded FMs in an ITER-sized mock-up of a first mirror unit (FMU) using wall materials with different sputtering energy thresholds (E th). Additionally, a part of the FM was electrically isolated from the RF to study its impact on the erosion/re-deposition properties on the surface. The E th of the wall materials, as well as its native oxide layers, had a significant influence on the re-deposition observed on the FMs. With high E th where walls were unsputtered, both the DC-grounded and electrically isolated parts of the FM were free of deposits. However, with low E th where the walls were sputtered, there was a net wall re-deposition on the DC-grounded parts of the FM, while electrically isolated parts were still relatively clean. Further, to study the impact of floating wall components, Cu walls in the FMU were isolated from the ground. Here the walls developed a floating potential V f and the ion energy at the walls was lowered to e(V p − V f). The floating walls, in this case, were relatively unsputtered and the FMs experienced a net cleaning with total reflectivity of the mirror preserved at pristine mirror levels. This work shows that electrically isolating the FM as well as the wall surface minimizes wall re-deposition in presence of λ/4 filter and therefore are promising techniques for effective FM cleaning in ITER.

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Three-dimensional simulation of neutral transport in gases and weakly ionized plasmas

Cited by 4 publications

References 29 publications

RF discharge mirror cleaning system development for ITER diagnostics

RF discharge mirror cleaning system development for ITER diagnostics

Three-dimensional modeling of sputtered materials transport in diagnostic ducts of fusion devices

Study of wall re-deposition on DC-grounded ITER-relevant mirrors with RF plasma in a first mirror unit

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