Tungsten erosion under plasma heat loads typical for ITER type I ELMs and disruptions

Garkusha, I.E.; Bandura, A. N.; Byrka, O.V.; Chebotarev, V. V.; Landman, I.; Makhlaj, V.A.; Marchenko, A. K.; Solyakov, D. G.; Tereshin, V.I.; Trubchaninov, S. A.; Tsarenko, A. V.

doi:10.1016/j.jnucmat.2004.10.008

Cited by 41 publications

(43 citation statements)

References 10 publications

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“…In earlier studies with QSPA Kh-50 [2,3] the tungsten targets had been exposed to a current-free hydrogen plasma. However, generally the plasma streams generated by QSPA can transport both heat and electric fluxes.…”

Section: Methodsmentioning

confidence: 99%

“…Droplet splashing and formation of craters with rather large edge ridges of displaced material have been investigated. For ITER ELM relevant loads of Q ELM $ 1 MJ/m 2 at t = 0.25-0.5 ms, the simulation experiments on exposure of tungsten plates at QSPA Kh-50 and macro-brush targets at QSPA-T demonstrated a much smaller effect of the pressure gradient [3,4]. In this case the Lorentz force can be one of the main mechanisms of melt layer erosion.…”

Section: Introductionmentioning

confidence: 92%

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Tungsten melt layer erosion due to J×B force under conditions relevant to ITER ELMs

Garkusha

Базылев

Bandura

et al. 2007

Journal of Nuclear Materials

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 92%

Tungsten melt layer erosion due to J×B force under conditions relevant to ITER ELMs

Garkusha

Базылев

Bandura

et al. 2007

Journal of Nuclear Materials

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“…In nuclear fusion research, one of the major concerns is the material erosion and damages accompanied with transient events called edge localized modes (ELMs) and disruption [1,2]. In addition to a steady heat load of ∼10 MWm −2 , the heat load to divertor plate in the mitigated type-I ELMs of ITER is likely to reach ∼0.5 MJm…”

Section: Introductionmentioning

confidence: 99%

“…To demonstrate the transient heat load, experiments using pulsed laser [3,4], plasma gun [2,5], and electron beam [6] have been conducted. Formation of various types of cracks and droplets were observed, and moreover, initiation of arcing in response to the transients was identified.…”

Section: Introductionmentioning

confidence: 99%

Superimposition of Pulses to Steady Arc Discharge in Toroidal Divertor Simulator

Kajita

Uchiyama

Ohno

2012

Plasma and Fusion Research

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A pulsed discharge was superimposed to a steady state arc discharge in the toroidal divertor simulator NAGDIS-T. The dynamic response of the plasma was observed with an electrostatic probe and fast framing camera. In the first loop plasma, which is close to the plasma source, the density becomes higher in response to the pulsed discharge, and the emission from the plasma significantly increases. On the other hand, in the second loop plasma, where a recombining plasma is formed, the emission from the plasma disappears in response to the pulse. Just after the pulsed discharge, plasma instabilities were formed and they were propagated from the upstream to downstream at the velocity of ∼10 km/s. After the series of pulsed plasma experiments, arc trails were recorded around the cathode area. On a molybdenum cover of the cathode, unipolar arcing was initiated on the surface. It is likely that the pulsed discharge leads to instabilities and initiate the unipolar arcing consequently.

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“…Some experiments with using quasi-steady-state plasma accelerator QSPA Kh-50 for analysis of the processes at the metal surfaces, including tungsten, under high heat plasma loading were carried out in previous our experiments [5,6]. In particular, melt layer motion due to the pressure gradient, some erosion characteristics of materials were investigated under heat loads relevant for disruptions and ELM's.…”

Section: Introductionmentioning

confidence: 99%

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

et al. 2006

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The results of experiments on powerful plasma stream -surface interaction in conditions of heat loads typical for current disruptions in reactor-tokamak ITER are presented here. The long pulse powerful plasma streams are generated with quasi-steady-state plasma accelerator QSPA Kh-50. The morphology of surfaces of tungsten and graphite, as well as surface of combined tungsten-graphite targets exposed to powerful plasma streams is analyzed. Some erosion properties of these materials are presented and compared with results of numerical simulations.PACS : 52.40.Hf

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Tungsten erosion under plasma heat loads typical for ITER type I ELMs and disruptions

Cited by 41 publications

References 10 publications

Tungsten melt layer erosion due to J×B force under conditions relevant to ITER ELMs

Tungsten melt layer erosion due to J×B force under conditions relevant to ITER ELMs

Superimposition of Pulses to Steady Arc Discharge in Toroidal Divertor Simulator

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

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