Manufacturing and high heat flux loading of tungsten coatings on fine grain graphite for the ASDEX-upgrade divertor

Deschka, S.; Garcı́a-Rosales, C.; Hohenauer, Wolfgang; Duwe, R.; Gauthier, E.; Linke, J.; Lochter, M.; Malléner, W.; Plöchl, L; Rödhammer, P.; Salito, A.

doi:10.1016/s0022-3115(96)00090-6

Cited by 42 publications

(18 citation statements)

References 3 publications

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“…For the outer target (tile 1) a 200 µm thick W coating deposited by vacuum plasma spraying (VPS) was used. A detailed description of the development of W coatings for ASDEX Upgrade is available in [13,14,15].…”

Section: Plasma Operationmentioning

confidence: 99%

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

et al. 2009

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Net erosion and deposition of tungsten in the ASDEX Upgrade divertor were determined after the 2007 campaign by using thin tungsten marker stripes. ASDEX Upgrade had full-tungsten plasmafacing components during this campaign. The inner divertor and the roof baffle were net W deposition areas with a maximum deposition of about 1×10 18 W-atoms/cm 2 in the private flux region below the inner strike point. Net erosion of W was observed in the whole outer divertor, with the largest erosion close to the outer strike point. Only a small fraction of the tungsten eroded in the main chamber and in the outer divertor was found in redeposits in the inner divertor, while a large fraction was either redeposited at unidentified places in the main chamber or has formed dust.

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Section: Plasma Operationmentioning

confidence: 99%

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

et al. 2009

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“…As coating technologies, VPS [44][45][46][47][48] and chemical vapor deposition (CVD), 49,50) have been proposed and tested in terms of the performances under high heat flux loading. Presently, VPS-W, density of more than 90% of sintered W has been achieved.…”

Section: )mentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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“…An alternative solution consists in coating the parts to protect with a W layer. Much work has been devoted to investigate suitable coating technologies and plasma spray (PS) in vacuum [2,9], physical vapor deposition (PVD) [10,11], and chemical vapor deposition (CVD) [12] have been proposed and tested under high heat flux loading. Yahiro et al [13] investigated air plasma spray (APS) comparing the characteristics of coatings with those obtained through PS made in vacuum.…”

Section: Introductionmentioning

confidence: 99%

Laser Pulse Effects on Plasma-Sprayed and Bulk Tungsten

Montanari

Pakhomova

Pizzoferrato

et al. 2017

Metals

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Tungsten (W) is considered a promising plasma-facing material for protecting the divertor of the ITER (International Thermonuclear Experimental Reactor). The effects on W of transient thermal loads of high energy occurring in a tokamak under operative conditions have been simulated through a single laser pulse delivered by an Nd:YAG laser. Bulk and plasma-sprayed (PS) samples have been submitted to tests and successively examined via SEM (scanning electron microscopy) observations. In both types of materials, the laser pulse induces similar effects: (i) a crater forms in the spot central area; (ii) all around the area, the ejection and the movement of molten metal give rise to a ridge; (iii) in a more external area, the surface shows plates with jagged boundaries and cracks induced by thermal stresses; (iv) the pores present in the original material become preferred ablation sites. However, the affected surface area in PS samples is larger and asymmetric if compared to that of bulk material. Such a difference has been explained by considering how microstructural characteristics influence heat propagation from the irradiated spot, and it was found that grain size and shape play a decisive role.

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Manufacturing and high heat flux loading of tungsten coatings on fine grain graphite for the ASDEX-upgrade divertor

Cited by 42 publications

References 3 publications

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Laser Pulse Effects on Plasma-Sprayed and Bulk Tungsten

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