Behavior of Capillary-Porous Systems with Liquid Lithium under Influence of Pulsed Deuterium Plasma

Vertkov, А.V.; Voronin, A. V.; Гусев, В. К.; Demina, E. V.; Lyublinskiy, I. E.; Пименов, В. Н.; Prusakova, M. D.

doi:10.1134/s2075113319020382

Cited by 4 publications

(4 citation statements)

References 7 publications

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“…Experimental studies of the liquid metal performance were carried out mostly with Li [2,6,7,[11][12][13]. The results presented in the papers [2,[11][12][13] have confirmed experimentally the compatibility of a lithium CPS with the plasma under real tokamak conditions, the capacity of the CPS to self-regenerate the exposed surface and to confine lithium during normal plasma operations and at disruptions, and the capability to withstand high heat loads without damage to the CPS surface. The behaviour of the CPS with liquid lithium under the impact of the pulsed deuterium plasma flows is considered in [12].…”

Section: Introductionmentioning

confidence: 79%

“…Such geometry was chosen based on the studies presented in [12,13]. A tin wire was placed on the bottom of the cap and melted in a vacuum on a free surface at a temperature of about (300-400) • C. In the next stage, the first mesh was attached to the target using a locking ring and heated in a vacuum until completely wetted.…”

Section: Experimental Facilities Samples and Diagnosticsmentioning

confidence: 99%

“…Capillary porous systems (CPSs) filled with liquid metal (Li, Sn) are considered now as an alternative approach for plasma-facing components of heavily loaded divertor in a fusion reactor [1,2]. This approach is comprehensively tested now using different plasma-surface interaction (PSI) devices [2,3,[5][6][7][8][9][10][11][12][13][14] as testbed facilities to analyse the material response to extremely high particle and heat fluxes attributed to the transient events like disruptions and repetitive giant ELMs. Among the favorable effects for the LM divertor approach could be a strong vapour shielding of exposed surfaces that decreases essentially both the resulting surface load and erosion.…”

Section: Introductionmentioning

confidence: 99%

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Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading

et al. 2021

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This paper presents experimental studies of plasma-surface interactions during powerful plasma impacts of a quasi-stationary plasma accelerator (QSPA) on the Sn capillary porous systems (CPSs) in conditions simulating disruption and edge localized modes (ELM) like loads. Experiments were carried out using two QSPA devices. ELM-like plasma exposures were performed with QSPA-M test-bed facility. A large-scale QSPA Kh-50 device was used to simulate plasma disruptions and giant ELMs. Variation of the plasma stream energy density has been performed to study the onset of vapour shield. It is shown that during plasma exposures of a Sn-CPS target with the QSPA plasma load <1 MJ m −2 , single dust particles traces have been registered. A further increase in the heat load leads to the splashing of the eroded material. For ELM-like impacts, a rather weak melt motion was observed on the target surface. A post-mortem analysis has shown that the CPS structure was not destroyed in the course of many repetitive ELM-like pulses. Surface morphology has changed from a smooth surface to corrugation structures with the formation of some cavities in mesh cells due to the influence of the surface tension and capillary effects. Spectral lines of Sn I and Sn II have been identified by optical emission spectroscopy in the near-surface plasma. A plasma shield, that consists mostly of Sn neutrals appears at Q ∼ 0.1 MJ m −2 . An increase in the surface heat load resulted in the intensive emission of Sn II lines, which started to be observed at Q ∼ 0.3 MJ m −2 . The plasma electron density near the surface increases significantly at Q > 0.5 MJ m −2 , which corresponds to the strong vapour shielding of the exposed surface. A comparison between the obtained results on the vapour shielding of Sn CPS and available numerical simulation using the TOKES code has been performed.

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Section: Introductionmentioning

confidence: 79%

Section: Experimental Facilities Samples and Diagnosticsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading

et al. 2021

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“…the isotropic radiation of part of the plasma power in the proximity of the target, leading to a beneficial selfregulation of the target heat load and, consequently, of the erosion rate [10,11]. These features, together with the absence of thermo-mechanical stresses at the interface between the CPS and the solid substrate [12], have the potential to guarantee a longer divertor lifetime and a superior resilience to transient events with respect to the current baseline solution [13].…”

Section: Introductionmentioning

confidence: 99%

SOLPS-ITER simulations of a CPS-based liquid metal divertor for the EU DEMO: Li vs Sn

Nallo¹,

Mazzitelli²,

Moscheni³

et al. 2022

Nucl. Fusion

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In this work, we study the effect of installing a liquid metal divertor (LMD) using a capillary-porous structure in the EU DEMO tokamak within the same envelope of the baseline solid divertor. We used the SOLPS-ITER code to model the Scrape-Off Layer (SOL) plasma and neutrals, coupled to a target thermal model to enable the self-consistent calculation of the LM target erosion rate, and adopting a fluid neutral model for the sake of simplicity. First calculations considering only D and Li (or Sn) showed a significant reduction of the steady state target heat load with respect to simulations considering only D, thanks to vapor shielding. Nevertheless, the computed peak target heat flux (~31 MW/m2 and ~44 MW/m2 for Li and Sn, respectively) was still larger than/borderline to the power handling limit of the LMD concepts considered. Moreover, the impurity concentration in the pedestal - a proxy for the core plasma dilution/contamination - was computed to be above/close to tolerability limits suggested by previous COREDIV calculations. These results indicate that the operational window of an LMD for the EU DEMO, without any additional impurity seeding, might be too narrow, if it exists, and that Sn looks more promising than Li. A second set of calculations was then performed simulating Ar seeding in the SOL, to further reduce the target heat load, and consequently the metal erosion rate. It was found that the mitigation of the plasma heat load due to Ar radiation in the SOL effectively replaces the radiation associated to vapor shielding in front of the target, thus allowing to operate the LMD in a regime of low target erosion. The resulting operational window was found to be significantly wider, both in terms of tolerable peak target heat flux and of acceptable core plasma contamination.

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Surface instability of static liquid metal in magnetized fusion plasma

Somboonkittichai

Zuo

2023

Nucl. Fusion

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Understanding surface instability in magnetized fusion plasma supports the appropriate implementation and handling of liquid metal as plasma facing components (PFCs) in future fusion reactors. A Lagrange equation describing a viscous liquid surface deformation in a magnetized plasma is derived using Rayleigh's method. Its solution justifies the general instability criterion and helps in characterizing the key interactions driving such instability under fusion conditions. Surface tension and gravity, especially with the poloidal angles of the lower part of a plasma chamber, mainly stabilize the liquid surface at small and large disturbance wavelengths, respectively. The sheath electric field and the external tangential magnetic field cause the liquid surface to disintegrate at an intermediate wavelength. Practically, a magnetic confinement fusion (MCF) device requires a strong magnetic field for confinement. The study suggests that such a strong field dominates the rest and governs instability. In addition, this implies that the configuration of a static planar free liquid surface is difficult to adopt as a candidate for handling the liquid metal as PFCs in next step MCF devices.

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Behavior of Capillary-Porous Systems with Liquid Lithium under Influence of Pulsed Deuterium Plasma

Cited by 4 publications

References 7 publications

Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading

Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading

SOLPS-ITER simulations of a CPS-based liquid metal divertor for the EU DEMO: Li vs Sn

Surface instability of static liquid metal in magnetized fusion plasma

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