Divertor heat flux reduction by D2 injection in DIII-D

Pétrie, T.W.; Buchenauer, D.; Hill, D. N.; Klepper, C. C.; Allen, Steven L.; Campbell, R. B.; Futch, A.H.; Groebner, R. J.; Leonard, A.W.; Lippmann, S.; Mahdavi, M. A.; Rensink, M.E.; West, P.

doi:10.1016/s0022-3115(06)80155-8

Cited by 114 publications

(50 citation statements)

References 7 publications

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“…The ARIES-RS outboard divertor plate peak heat flux is estimated by considering the net power reaching the plate with significant fraction of power, f c , already lost by radiation in the core as shown in Table 1. In this estimation, the expected bremsstrahlung and line radiation losses in the core, and the up/down and inboard/outboard distributions of scrape-off layer power flow are consistent with the experimental database from ASDEX, PDX and DIII-D double-null operation [1]. The in/out power balance at the divertor is consistent with the single-null ELMing H-mode results from DIII-D [2].…”

Section: Initial Peak Heat Flux Estimationsupporting

confidence: 83%

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ARIES-RS divertor system selection and analysis

Wong

Chin

Pétrie

et al. 1997

Fusion Engineering and Design

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Section: Initial Peak Heat Flux Estimationsupporting

confidence: 83%

“…Scaling Tokamak experimental results of DIII-D [1] to the size and power flux of ARIES-RS, the divertor maximum heat flux is estimated to be much higher than the design goal of 5 MW m − 2 . Using Ne as the radiating impurity, and by assuming a Ne enrichment factor of 8 at the divertor, the maximum heat flux is reduced to B 6 MW m − 2 .…”

Section: Introductionmentioning

confidence: 94%

ARIES-RS divertor system selection and analysis

Wong

Chin

Pétrie

et al. 1997

Fusion Engineering and Design

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“…Under certain conditions related to the detachment state [10] the D α radiation in the outer divertor shows a strong increase at the same time. Correlated with these processes, the current I pol,sol,out has a strong rise in absolute value [11].…”

Section: Elm Dynamics Of Typical Edge Quantitiesmentioning

confidence: 98%

Solitary magnetic perturbations at the ELM onset

et al. 2012

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Tokamak H-mode plasmas frequently exhibit edge-localized modes (ELMs). ELMs allow maintaining sufficient plasma purity and thus enable stationary H-mode. On the other hand in a future device ELMs may cause divertor power flux densities far in excess of tolerable material limits. The size of the energy loss per ELM is determined by saturation effects in the non-linear phase of the ELM, which at present is hardly understood. ASDEX Upgrade is now equipped with a set of fast sampling diagnostics, which is well suited to investigate the chain of events around the ELM crash with appropriate temporal resolution ( 10 µs).Solitary magnetic perturbations (SMPs) are identified as dominant features in the radial magnetic fluctuations below 100 kHz. They are typically observed close (±100 µs) to the onset of pedestal erosion. SMPs are field aligned structures rotating in the electron diamagnetic drift direction with perpendicular velocities of about 10 km s −1 . A comparison of perpendicular velocities suggests that the perturbation evoking SMPs is located at or inside the separatrix. Analysis of very pronounced examples showed that the number of peaks per toroidal turn is 1 or 2, which is clearly lower than the corresponding numbers in linear stability calculations. In combination with strong peaking of the magnetic signals this results in a solitary appearance resembling modes like palm tree modes, edge snakes or outer modes. This behaviour has been quantified as solitariness and correlated with main plasma parameters.SMPs may be considered as a signature of the non-linear ELM phase originating at the separatrix or further inside. Thus they provide a handle to investigate the transition from linear to non-linear ELM phase. By comparison with data from gas puff imaging processes in the non-linear phase at or inside the separatrix and in the scrape-off layer (SOL) can be correlated. A connection between the passing of an SMP and the onset of radial filament propagation has been found. Eventually the findings related to SMPs may contribute to a future quantitative understanding of the non-linear ELM evolution.

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“…Matsubara et al 2006;Hayashi et al 2016) and the tokamaks (see e.g. Petrie et al 1992;Asakura et al 1996;Wenzel et al 1997;Loarte et al 1999;Potzel et al 2013;Reimold et al 2015b). In the tokamaks, the frequency of these fluctuations varies from device to device and spans over a range from ∼10 Hz (Loarte et al 1999) to ∼10 kHz (Potzel et al 2013), which suggests that the physical mechanisms of these fluctuations are different.…”

Section: Transient Effects In the Detached Divertor Regimementioning

confidence: 99%

Physics of ultimate detachment of a tokamak divertor plasma

Krasheninnikov¹,

2017

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The basic physics of the processes playing the most important role in divertor plasma detachment is reviewed. The models used in the two-dimensional edge plasma transport codes that are widely used to address different issues of the edge plasma physics and to simulate the experimental data, as well as the numerical schemes and convergence issues, are described. The processes leading to ultimate divertor plasma detachment, the transition to and the stability of the detached regime, as well as the impact of the magnetic configuration and divertor geometry on detachment, are considered. A consistent, integral physical picture of ultimate detachment of a tokamak divertor plasma is developed.

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Divertor heat flux reduction by D2 injection in DIII-D

Cited by 114 publications

References 7 publications

ARIES-RS divertor system selection and analysis

ARIES-RS divertor system selection and analysis

Solitary magnetic perturbations at the ELM onset

Physics of ultimate detachment of a tokamak divertor plasma

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