In-vessel dust and tritium control strategy in ITER

Shimada, M.; Pitts, R.A.; Ciattaglia, S.; Carpentier, S.; Choi, Changhwan; Orco, Giovanni Dell; Hirai, T.; Kukushkin, A. S.; Lisgo, S.; Palmer, J.; Shu, W.M.; Veshchev, E.

doi:10.1016/j.jnucmat.2013.01.217

Cited by 77 publications

(49 citation statements)

References 24 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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“…In these cases the heat loads can reach energy density Q h =5-80 MJm -2 , power density q h =5-25 GWm -2 over the heating time h =0.3-3 ms for type I ELMs and major disruption. These heat loads correspond to maximal heat flux parameter values F HF =600-2000 MJ m -2 s -0.5 [1,2]. Such extremal impacts go well beyond the conditions in the modern tokamaks.…”

Section: Introductionmentioning

confidence: 99%

Novel electron beam based test facility for observation of dynamics of tungsten erosion under intense ELM-like heat loads

Vyacheslavov

Arakcheev

Бурдаков

et al. 2016

AIP Conference Proceedings

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“…Such heat loads can reach energy density of 5-80 MJm -2 , power density of 5 -25 GWm -2 and the heating time of 0.3 -3 ms [1,2]. The heightened erosion is associated with creation of melt layer and ejection of dust particles.…”

Section: Introductionmentioning

confidence: 99%

Observation of dust particles ejected from tungsten surface under impact of intense transient heat load

Kasatov¹,

Arakcheev²,

Burdakov³

et al. 2016

AIP Conference Proceedings

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In-vessel dust and tritium control strategy in ITER

Cited by 77 publications

References 24 publications

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

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

Novel electron beam based test facility for observation of dynamics of tungsten erosion under intense ELM-like heat loads

Observation of dust particles ejected from tungsten surface under impact of intense transient heat load

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