Experimental study of PFCs erosion and eroded material deposition under ITER-like transient loads at the plasma gun facility QSPA-T

Климов, Н. С.; Podkovyrov, V. L.; Zhitlukhin, A.M.; Коваленко, Д. В.; Linke, J.; Pintsuk, G.; Landman, I.; Pestchanyi, S.; Базылев, Б.; Janeschitz, G.; Loarte, A.; Merola, M.; Hirai, T.; Federici, G.; Riccardi, B.; Mazul, I.; Giniyatulin, R.; Khimchenko, L. N.; Koǐdan, V. S.

doi:10.1016/j.jnucmat.2011.01.013

Cited by 66 publications

(33 citation statements)

References 16 publications

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“…In case the impinging particle is still liquid, the impact is systematically treated as sticking, on the basis that the spreading dynamics of the colliding droplet likely result in a large contact area, allowing fast solidification via heat transfer to the colder wall as observed in [30,69] (see section 4.3 for estimations of such heat transfer in the case of small contact areas). For re-solidified dust, the collisions are treated according to the elastic-perfectly plastic adhesive sphere-surface impacts model by Thornton and Ning [22,70], recently validated for micrometer-scale W dust against experimental observations of grain-surface collisions in the sheath of magnetized plasmas [69,71].…”

Section: Collisions With the Vessel Wallmentioning

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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Section: Collisions With the Vessel Wallmentioning

confidence: 99%

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

et al. 2018

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“…The energy load limit currently forseen for the ITER divertor targets is 0.5 MJ/m² for ELM pulses with 0.5 ms duration, based on results from numeric simulations and experimental studies [1,8,9,10]. Among other devices, the Triniti divertor material test facility QSPA-T is used for the qualification of plasma facing components during transient heat loads as expected during ELMs and disruptions in ITER [9].…”

Section: Temporal Characterization Of Elm Shapesmentioning

confidence: 99%

Power load characterization for type-I ELMy H-modes in JET

et al. 2011

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Abstract.ELM resolved divertor target power load studies were conducted for a wide range of discharge conditions in the JET tokamak. The magnetic configuration of these discharges was optimized for the fast divertor IR camera observing the outboard target. It is found that the ELM size estimated from the diamagnetic energy is not uniquely determining the ELM energy load at the divertor target. ELM mid plane integral deposited power widths between 7 * See the Appendix of F. Romanelli et al., Proceedings of the 23rd IAEA Fusion Energy Conference 2010, Daejeon, Korea 2 mm and 18 mm are observed, the inter-ELM widths lie in a range of 2.5 mm to 6 mm. This ELM broadening is found to widen with ELM size. The temporal evolution of the ELM shape was characterized by rise and decay times. The ELM rise times are found to be in the range expected for ITER (250 µs), but the ELM decay is usually larger than assumed for the ITER design.

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“…1 But if too large, they cause large heat fluxes which can damage plasma facing components. 2, 3 As the ability of controlling the ELM properties decides on whether the H-mode can be a suitable operational regime for ITER and future fusion reactors, the understanding of this instability is crucial. Nonlinear MHD simulations are an important tool in the quest for theoretical comprehension of ELMs.…”

Section: Introductionmentioning

confidence: 99%

Nonlinear excitation of low-n harmonics in reduced magnetohydrodynamic simulations of edge-localized modes

et al. 2013

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Nonlinear simulations of the early edge-localized mode (ELM) phase based on a typical type-I ELMy ASDEX Upgrade discharge have been carried out using the reduced MHD code JOREK. The analysis is focused on the evolution of the toroidal Fourier spectrum. It is found that during the nonlinear evolution, linearly subdominant low-n Fourier components, in particular the n ¼ 1, grow to energies comparable with linearly dominant harmonics. A simple model is developed, based on the idea that energy is transferred among the toroidal harmonics via second order nonlinear interaction. The simple model reproduces and explains very well the early nonlinear evolution of the toroidal spectrum in the JOREK simulations. Furthermore, it is shown for the n ¼ 1 harmonic, that its spatial structure changes significantly during the transition from linear to nonlinearly driven growth. The rigidly growing structure of the linearly barely unstable n ¼ 1 reaches far into the plasma core. In contrast, the nonlinearly driven n ¼ 1 has a rigidly growing structure localized at the plasma edge, where the dominant toroidal harmonics driving the n ¼ 1 are maximal and in phase. The presented quadratic coupling model might explain the recent experimental observation of strong low-n components in magnetic measurements [Wenninger et al., "Non-linear magnetic perturbations during edge localized modes in TCV dominated by low n mode components," Nucl. Fusion (submitted)]. [http://dx.

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Experimental study of PFCs erosion and eroded material deposition under ITER-like transient loads at the plasma gun facility QSPA-T

Cited by 66 publications

References 16 publications

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

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

Power load characterization for type-I ELMy H-modes in JET

Nonlinear excitation of low-n harmonics in reduced magnetohydrodynamic simulations of edge-localized modes

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