Erosion mechanism and erosion products in carbon-based materials

Arkhipov, N.I.; Bakhtin, V. P.; Barsuk, V.A.; Kurkin, Semen A.; Mironova, E. G.; Piazza, G.; Safronov, V.M.; Scaffidi-Argentina, F.; Toporkov, D. A.; Vasenin, S.G.; Würz, H.; Zhitlukhin, A.M.

doi:10.1016/s0022-3115(02)00963-7

Cited by 10 publications

(15 citation statements)

References 17 publications

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“…The speeds of the released particles were estimated to be around 10 m/s for graphite and W by laser scattering measurement. 119,120) The speed is one order of magnitude slower than the one measured in the electron beam facility, JUDITH.…”

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 92%

“…A minor drawback is the inflexible pulse duration: the duration is fixed at several tens of ms in plasma guns 101,[118][119][120][121][122] and several hundred ms in quasi-stationary plasma guns.…”

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

“…Figure 8 shows a plasma gun MK-200 UG in Troitsk (Russia). 120) Plasma guns are suitable facilities to study the shielding effect under disruption. Due to interaction of energetic plasma pulse with solid material, vaporization of a thin surface layer and a cloud of dense vapor plasma are produced.…”

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

“…As a result, shielding factors (incident energy/energy used by thermal erosion) estimated to be 500 in graphite, above 1000 in CFC and 100 in W at an incident energy Q ¼ 15 MJ/m 2 in MK-200UG. 119,120) The effect of magnetic field enhances the shielding effect by the confinement of a vapor cloud (vapor shield) in front of the targets. It indicates a considerable reduction of energy influx for plasma disruptions in fusion devices.…”

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

“…Erosion product (particle) size distribution was found mostly 1-3 mm in graphite and CFC and 1-200 mm for W droplets in MK-200UG. 101,119,120) The contribution of BD in graphite, ratio of graphite crystalline in the collected deposits, was estimated to be about 10% and the contribution of BD in CFC was considered to be even less in MK-200UG. 119) On the other hand, the size distribution of W particles had a narrow distribution from 0.1 to $3 mm and CFC had a wide distribution from 0.01 to $40 mm in MKT plasma gun.…”

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

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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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Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 92%

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

Section: Transient Heat Load Testing By Other Heat Sources 421 Thermentioning

confidence: 99%

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ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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Application of Magnetized Coaxial Plasma Guns for Simulation of Transient High Heat Loads on ITER Divertor

Nagata

Kikuchi

Fukumoto

2009

IEEJ Transactions Elec Engng

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The magnetized coaxial plasma gun (MCPG) was investigated to seek possibilities of its application for a transient high heat testing to the ITER divertor surfaces. The experimental results showed that the MCPG could generate the hydrogen plasma stream with the ion energy of 50 eV, the peak energy density of 0.7 MJ/m2 and the discharge duration of ∼0.05 ms. This capability is enough powerful to melt tungsten materials. Vaporization of a thin surface layer and a cloud of dense vapor plasma in front of the carbon calorimeter were observed by spectroscopic measurements. © 2009 Institute of Electrical Engineers of Japan. Published by John Wiley & Sons, Inc.

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Simulation of dust production in ITER transient events

Pestchanyi¹,

Landman²

2008

Fusion Engineering and Design

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Erosion mechanism and erosion products in carbon-based materials

Cited by 10 publications

References 17 publications

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Application of Magnetized Coaxial Plasma Guns for Simulation of Transient High Heat Loads on ITER Divertor

Simulation of dust production in ITER transient events

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