Dust limit management strategy in tokamaks

Rosanvallon, S.; Grisolia, Christian; Andrew, P.; Ciattaglia, S.; Delaporte, Ph.; Douai, D.; Garnier, D.; Gauthier, E.; Gulden, W.; Hong, Suk–Ho; Pitcher, S.; Rodrı́guez, L.; Taylor, Neill; Tesini, A.; Vartanian, S.; Vatry, A.; Wykes, M.

doi:10.1016/j.jnucmat.2009.01.048

Cited by 37 publications

(20 citation statements)

References 10 publications

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“…For these reasons, the ITER Licensing agreement requires that the quantity of dust in the vacuum vessel must remain below given limits [1][2][3][4]. The maximum amount of mobilizable dust in the vessel is 1000 kg.…”

Section: Introductionmentioning

confidence: 99%

Survival and in-vessel redistribution of beryllium droplets after ITER disruptions

et al. 2018

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The motion and temperature evolution of beryllium droplets produced by first wall surface melting after ITER major disruptions and vertical displacement events mitigated during the current quench are simulated by the MIGRAINe dust dynamics code. These simulations employ an updated physical model which addresses droplet-plasma interaction in ITER-relevant regimes characterized by magnetized electron collection and thin-sheath ion collection, as well as electron emission processes induced by electron and high-Z ion impacts. The disruption scenarios have been implemented from DINA simulations of the time-evolving plasma parameters, while the droplet injection points are set to the first-wall locations expected to receive the highest thermal quench heat flux according to field line tracing studies. The droplet size, speed and ejection angle are varied within the range of currently available experimental and theoretical constraints, and the final quantities of interest are obtained by weighting single-trajectory output with different size and speed distributions. Detailed estimates of droplet solidification into dust grains and their subsequent deposition in the vessel are obtained. For representative distributions of the droplet injection parameters, the results indicate that at most a few percents of the beryllium mass initially injected is converted into solid dust, while the remaining mass either vaporizes or forms liquid splashes on the wall. Simulated in-vessel spatial distributions are also provided for the surviving dust, with the aim of providing guidance for planned dust diagnostic, retrieval and clean-up systems on ITER.

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Section: Introductionmentioning

confidence: 99%

Survival and in-vessel redistribution of beryllium droplets after ITER disruptions

et al. 2018

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“…The formation and accumulation of dust may have a serious impact on the economy and safety in operation of a reactor-class device [3,[10][11][12][13]. The primary concern is related to consequences of oxygen and/or water contact with hot dust in the case of air and/or water leak during the plasma operation giving a high risk of pressure rise and explosion.…”

Section: Introductionmentioning

confidence: 99%

Survey of dust formed in the TEXTOR tokamak: structure and fuel retention

et al. 2009

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A detailed survey of erosion and deposition on plasma-facing components was performed in the TEXTOR tokamak. Co-deposits and dust particles were collected from graphite limiters and from several locations on the Inconel liner. The total amount of dust (loose material), originating mainly from carbon-rich co-deposits detached from the limiters and the liner, was around 2 g, with sizes from 0.1 µm to 1 mm. The morphology and fuel retention was determined using microscopy methods, ion beam analysis and thermal desorption spectrometry. The study revealed differences in structure and fuel content between deposits from the toroidal and main poloidal limiters. There were also splashes, up to 1 mm in diameter, of molten metal (mainly nickel) on the toroidal limiters. Issues of the dust conversion factor (erosion-to-dust) are addressed and a comparison with results of previous dust surveys at TEXTOR is also briefly presented.

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“…Dust particles can penetrate to the core plasma, leading to operational problems such as reduced plasma confinement [7]. The maximum quantity of dust particles in the International Thermonuclear Experimental Reactor is limited to less than 6 kg of carbon or 11 kg of beryllium and 230 kg of tungsten [8,9]. It is critical to reduce dust accumulation for long-term operation of fusion reactors.…”

Section: Introductionmentioning

confidence: 99%