Vertical target and FW erosion during off-normal events and impurity production and transport during ELMs typical for ITER-FEAT

Würz, H.; Pestchanyi, S.; Базылев, Б.; Landman, I.; Kappler, F.

doi:10.1016/s0022-3115(00)00478-5

Cited by 28 publications

(4 citation statements)

References 7 publications

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“…If the highest observed energy density, 1 MJ m −2 , is scaled from the typical MkIIGB stored energies (thermal ∼10 MJ and magnetic ∼50 MJ) to those expected for ITER (thermal ∼300 MJ and magnetic ∼1500 MJ), it would lead, even without accounting for a beneficial increase in wetted area (proportional to the square of the ratio of their major radius), to an energy density ∼30 MJ m −2 . This is within the present ITER assumptions, 50 MJ m −2 [19].…”

Section: Discussionsupporting

confidence: 87%

Disruption heat loads on the JET MkIIGB divertor

Riccardo

Andrew

Ingesson

et al. 2002

Plasma Phys. Control. Fusion

140

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Combined analysis of divertor thermocouple and IR camera measurements during JET disruptions can provide valuable information on the distribution of the energy loads, even if the stored energy of the JET plasmas is small compared to that foreseen for the next-generation tokamaks. Typically the energy collected at the divertor represents a small fraction of the pre-disruption plasma energy; this is consistent with the high level of radiation observed and with part of the magnetic energy being transferred to the plasma-coupled conductors.The data for this paper are taken from the whole set of disruptive plasmas of JET operation in the years 2000 and 2001. In most of the MkIIGB disruptions, the plasma displaces upwards (away from the divertor); therefore, only a small number of downward events are available for analysis. However, divertor heat loads seem to be more strongly correlated to the delay of the loss of the X-point with respect to the thermal quench than the direction of the plasma displacement.When the plasma thermal energy is lost with the plasma still in X-point configuration, the septum and the tiles wetted by the strike-points, often more than one tile per strike-point, experience a sharp increase in temperature, equivalent to up to 1 MJ m −2 . When the thermal quench occurs at the same time as, or after, the loss of plasma vertical control, no significant divertor tile temperature increase can be observed for both upwards and downwards events. Most of the disruptions purposely made to produce runaway electrons went towards the divertor and, although not systematically, lead to local (mostly at the septum) temperature increase equivalent to a load up to 2 MJ m −2 , often toroidally asymmetric.

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Section: Discussionsupporting

confidence: 87%

Disruption heat loads on the JET MkIIGB divertor

Riccardo

Andrew

Ingesson

et al. 2002

Plasma Phys. Control. Fusion

140

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“…This means 10 6 ELM loads can easily be achieved in the lifetime of a PFC [57][58][59][60][61]. Other transient events occur during off-normal operation and are much less frequent (~10 3 ): the thermal quench of disruptions (30 MJ m −2 in 1-10 ms), vertical displacement events (VDEs, 60 MJ m −2 in 100-300 ms) and runaway electrons (50 MJ m −2 in <50 ms) [61][62][63]. The mitigation of transient events by massive gas injection (MGI) leads to photon flashes which have an energy density comparable to ELMs (0.9-1.3 MJ m −2 , ~3 ms), but only ~1000 of these are expected during first wall lifetime [64,65].…”

Section: Stationary and Thls In Fusion Devicesmentioning

confidence: 99%

Baseline high heat flux and plasma facing materials for fusion

et al. 2017

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In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).

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“…Many plasma processes, such as brittle destruction [4] , volume polymerization [5] , cracking development [6] , arcing [7] , flaking of blisters [8] and surface melting [9] etc., contribute to the production of dust particles. Off-normal plasma events such as edge localized mode (ELM) [10,11] also play a significant role in dust generation. Dust particles increase the operation difficulties of plasma sustainment since dust is a source of impurities and facilitates radiation power [12] .…”

Section: Introductionmentioning

confidence: 99%

Molecular Dynamics Simulations of the Interactions Between Tungsten Dust and Beryllium Plasma-Facing Material

Niu

et al. 2015

Plasma Sci. Technol.

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In the present research, molecular dynamics simulation is applied to study the interactions between tungsten dusts and a beryllium plasma-facing material surface. Calculation results show that it is quite difficult for nanometer-size dust particles to damage the plasma-facing material surface, which is different from the micrometer-size ones. The reason may be the size difference between dust and crystal grains. The depth of dust penetration into plasma-facing materials is closely related to the incident velocity, and the impacting angle also plays an important role. Dust and material surface damage is also investigated. Results show that both incident velocity and angle can significantly influence the damage.

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Vertical target and FW erosion during off-normal events and impurity production and transport during ELMs typical for ITER-FEAT

Cited by 28 publications

References 7 publications

Disruption heat loads on the JET MkIIGB divertor

Disruption heat loads on the JET MkIIGB divertor

Baseline high heat flux and plasma facing materials for fusion

Molecular Dynamics Simulations of the Interactions Between Tungsten Dust and Beryllium Plasma-Facing Material

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