Impact of liquid metal surface on plasma-surface interaction in experiments with lithium and tin capillary porous systems

Budaev, V. P.; Lyublinsky, I. E.; Fedorovich, S. D.; Дедов, А. В.; Vertkov, А.V.; Komov, A. T.; Karpov, A. V.; Martynenko, Yu. V.; Oost, G. Van; Gubkin, M. K.; Lukashevsky, M. V.; Marchenkov, A. Yu.; Rogozin, K. A.; Vasiliev, G.B.; Konkov, A.A.; Lazukin, A. V.; Zakharenkov, A. V.; Zakletsky, Z A

doi:10.1016/j.nme.2020.100834

Cited by 5 publications

(2 citation statements)

References 17 publications

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“…It was experimentally demonstrated both in tokamaks [4][5][6] * Author to whom any correspondence should be addressed. and linear plasma devices [7][8][9] that the CPS components can withstand relevant stationary heat loads of at least 15 MW m −2 and even higher pulsed loads characteristic for non-steadystate events, e.g. edge localized modes (ELMs) or disruptions.…”

Section: Introductionmentioning

confidence: 99%

Simulation of lithium flow, redeposition, and vapor shielding in liquid lithium divertor of T-15MD tokamak with SOLPS 4.3 code

Marenkov¹,

Pshenov²,

Kukushkin³

2022

Plasma Phys. Control. Fusion

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The erosion module of the SOLPS 4.3 code package for the liquid Li divertor target is developed to include the thermal sputtering, evaporation, and prompt redeposition effects. Eroded Li atoms are treated within a fully kinetic approach. Simulations of the T-15MD tokamak with liquid Li divertor targets are performed for various operational regimes. The main parameters characterizing the divertor operation are identified. The Li shielding effect is found significant at the input power PSOL > 15 MW. The target conditions remain reasonable in terms of both the erosion rate and target temperature but core plasma dilution with Li remains a problem. The Li flow patterns in the scrape-of-layer (SOL) are analyzed in detail. About 80% of eroded Li is redeposited back on the target. The energy dissipated per an eroded Li particle, Esh, is calculated and its values are in the range of 100-200 eV. We show that these values are 2-4 times lower than those obtained from a simple 0D estimation of Esh. Therefore, relying on simple 0D models for the analysis of Li divertor performance may cause an overestimation of the shielding efficiency.

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Section: Introductionmentioning

confidence: 99%

Simulation of lithium flow, redeposition, and vapor shielding in liquid lithium divertor of T-15MD tokamak with SOLPS 4.3 code

Marenkov¹,

Pshenov²,

Kukushkin³

2022

Plasma Phys. Control. Fusion

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“…However, there are a number of problems, associated with the high evaporation rate of lithium in a vacuum at high temperatures. An innovative solution to these problems is the use of tin-lithium eutectics as a plasma-facing material [11][12][13], which has lower vaporization parameters in a vacuum. Due to the fact that tin-lithium eutectic is a relatively new candidate material, there is a need to study of the properties of this material in detail.…”

Section: Introductionmentioning

confidence: 99%

Determination of thermophysical properties of prototypes of tin-lithium alloy by differential scanning calorimetry

Bochkov

Ponkratov

Nikitenkov

et al. 2022

J. Phys.: Conf. Ser.

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This paper presents a description of research works to determine the thermophysical properties of a tin-lithium alloy with a different percentage of lithium and tin atoms in the alloy. The method of differential scanning calorimetry (DSC) was used for the studies, by which the thermophysical properties of the alloy (temperature of phase transition and enthalpy) were determined. The work was carried out at the TiGrA experimental complex. Studies to determine the enthalpy and temperature of phase transition of prototypes of tin-lithium alloy were carried out in the temperature range from 150°C to 500°C at a heating rate of 10°C/min. The experiments were carried out with a pristine sample of tin (reference) and prototypes of a tin-lithium alloy, the percentage of lithium in which was 20, 25 and 27 at. %. As a result of the work performed, the melting point of the prototypes was determined, which was 224°C and 218°C. The values of the specific heat of fusion (enthalpy) of the investigated alloys were determined, which amounted to 76.5 J/g, 80.7 J/g and 86.3 J/g, respectively.

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Reducing tin droplet ejection from capillary porous structures under hydrogen plasma exposure in Magnum-PSI

Scholte

Иафрати²,

Lam

et al. 2023

Nuclear Materials and Energy

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Impact of liquid metal surface on plasma-surface interaction in experiments with lithium and tin capillary porous systems

Cited by 5 publications

References 17 publications

Simulation of lithium flow, redeposition, and vapor shielding in liquid lithium divertor of T-15MD tokamak with SOLPS 4.3 code

Simulation of lithium flow, redeposition, and vapor shielding in liquid lithium divertor of T-15MD tokamak with SOLPS 4.3 code

Determination of thermophysical properties of prototypes of tin-lithium alloy by differential scanning calorimetry

Reducing tin droplet ejection from capillary porous structures under hydrogen plasma exposure in Magnum-PSI

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