Study of brittle destruction and erosion mechanisms of carbon-based materials during plasma instabilities

Burtseva, T.A.; Hassanein, A.; Ovchinnikov, I.; Титов, В. А.

doi:10.1016/s0022-3115(00)00663-2

Cited by 12 publications

(5 citation statements)

References 4 publications

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“…However, the generation of dust particles due to brittle destruction observed during Tokamak operation or in severe thermal shock experiments, arouse critical safety issue in future fusion devices. 41,42…”

Section: Resultsmentioning

confidence: 99%

Late-time particle emission from laser-produced graphite plasma

Harilal¹,

Hassanein²,

Polek³

2011

Journal of Applied Physics

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We report a late-time "fireworks-like" particle emission from laser-produced graphite plasma during its evolution. Plasmas were produced using graphite targets excited with 1064 nm Nd: yttrium aluminum garnet (YAG) laser in vacuum. The time evolution of graphite plasma was investigated using fast gated imaging and visible emission spectroscopy. The emission dynamics of plasma is rapidly changing with time and the delayed firework-like emission from the graphite target followed a black-body curve. Our studies indicated that such firework-like emission is strongly depended on target material properties and explained due to material spallation caused by overheating the trapped gases through thermal diffusion along the layer structures of graphite. V C 2011 American Institute of Physics.

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Section: Resultsmentioning

confidence: 99%

Late-time particle emission from laser-produced graphite plasma

Harilal¹,

Hassanein²,

Polek³

2011

Journal of Applied Physics

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“…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%

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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“…In [2] semi-spherical formations with a stratified structure were found on the surface of three-dimensional CFC of UAM type (PAN fibers) under irradiation in the plasma accelerator VIKA-93 (energy of plasma beam 30 MJ/m 2 , pulse duration 300 ls, T > 2300 K). In both cases surface modifications were considered The hydrogen retention were mainly studied for dense graphites in the ion beam facilities with impinging ion energy not exceeding 1000 eV [3][4][5].…”

Section: Introductionmentioning

confidence: 99%