Physics basis and design of the ITER plasma-facing components

Pitts, R.A.; Carpentier, S.; Escourbiac, F.; Hirai, T.; Komarov, V.; Kukushkin, A.S.; Lisgo, S.; Loarte, A.; Merola, M.; Mitteau, R.; Raffray, A.R.; Shimada, M.; Stangeby, P.C.

doi:10.1016/j.jnucmat.2011.01.114

Cited by 397 publications

(268 citation statements)

References 25 publications

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“…Taking into account that parts of the ITER first wall can handle q ⊥ = 2 MWm −2 only [15] and ITER has to operate at high p 0,div and P sep , this calls for further investigation.…”

Section: Features Of the High Cross-field Transport Regimementioning

confidence: 99%

Far scrape-off layer particle and heat fluxes in high density – High power scenarios

Müller

Bernert

Carralero

et al. 2015

Journal of Nuclear Materials

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The transport across the far scrape-off layer is studied in ASDEX Upgrade for ITER relevant scenarios with high divertor neutral pressure, high power across the separatrix and nitrogen seeding to control the divertor temperature. With high divertor neutral pressure and high power across the separatrix H-mode discharges enter a regime of high cross-field particle and power transport in the far SOL. In

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“…Taking into account that parts of the ITER first wall can handle q ⊥ = 2 MWm −2 only [15] and ITER has to operate at high p 0,div and P sep , this calls for further investigation.…”

Section: Features Of the High Cross-field Transport Regimementioning

confidence: 99%

Far scrape-off layer particle and heat fluxes in high density – High power scenarios

Müller

Bernert

Carralero

et al. 2015

Journal of Nuclear Materials

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“…The next step on the road to fusion power plant is the International Thermonuclear Experimental Reactor (ITER) project whose main scientific goal is to deliver ten times the power it consumes [1] -and the first of all fusion experiments to produce net energy. During the first operation period of the ITER reactor according to the current design plasma facing components shall be made of beryllium (on the first wall) and of tungsten and carbon-fibre reinforced carbon (CFC) (in the divertor) [2]. Further operation of ITER, including the use of tritium as a fuel, might require a full W divertor [3].…”

Section: Introductionmentioning

confidence: 99%

Carbide formation in tungsten coatings on carbon-fibre reinforced carbon substrates

et al. 2013

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Tungsten coatings with molybdenum interlayer deposited on carbon-fibre reinforced carbon (CFC) substrates were selected as the first wall material for the divertor in the ITERlike Wall Project at Joint European Torus. For such a layered structure, diffusion of carbon from the CFC substrate towards the Mo and W deposits is expected during the operation of the reactor. As both molybdenum and tungsten form stable carbides, brittle compounds may form at the interface, thus strongly affecting the thermomechanical performance of the coated tiles. For the purpose of prediction of the operation time of such coated tiles, carbon diffusion and carbide formation kinetics need to be determined.In the present study, W/Mo/CFC samples were subjected to heat treatment at 1470 K for various annealing times. The Focused Ion Beam technique was used for sample preparation for electron microscopy examinations. Transmission electron microscopy observations supported with diffraction pattern analyses revealed the both W 2 C and WC carbides in the W coating, as well as that of Mo 2 C carbide in the Mo layer. The results were used to estimate the kinetics of coatings degradation.2

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“…The divertor plasma in ITER will be characterized by a high density (≥ 10 21 m −3 ) and a low electron temperature (T e ≤ 5 eV) leading to high heat (≥ 10 MW·m −2 ) and particle fluxes (up to 10 24 m −2 s −1 or 1.6×10 5 A·m −2 ) [1]. Assuming ion acceleration in the electrostatic sheath, the ions will have energies below 50 eV, at the divertor strike-point.…”

Section: Introductionmentioning

confidence: 99%

High heat flux capabilities of the Magnum-PSI linear plasma device

Temmerman

Berg

Scholten

et al. 2013

Fusion Engineering and Design

108

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Magnum-PSI is an advanced linear plasma device uniquely capable of producing plasma conditions similar to those expected in the divertor of ITER both steady-state and transients. The machine is designed both for fundamental studies of plasma-surface interactions under high heat and particle fluxes, and as a high-heat flux facility for the tests of plasma-facing components under realistic plasma conditions. To study the effects of transient heat loads on a plasma-facing surface, a novel pulsed plasma source system as well as a high power laser are available. In this article, we will describe the capabilities of Magnum-PSI for high-heat flux tests of plasma-facing materials.

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Physics basis and design of the ITER plasma-facing components

Cited by 397 publications

References 25 publications

Far scrape-off layer particle and heat fluxes in high density – High power scenarios

Far scrape-off layer particle and heat fluxes in high density – High power scenarios

Carbide formation in tungsten coatings on carbon-fibre reinforced carbon substrates

High heat flux capabilities of the Magnum-PSI linear plasma device

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