High performance H mode plasmas at densities above the Greenwald limit

Mahdavi, M. A.; Osborne, T.H.; Leonard, A.W.; Chu, M. S.; Doyle, E. J.; Fenstermacher, M.E.; McKee, G. R.; Staebler, G. M.; Pétrie, T.W.; Wade, M. R.; Allen, S. L.; Boedo, J.A.; Brooks, N.H.; Colchin, R.J.; Evans, T.E.; Greenfield, C. M.; Porter, G. D.; Isler, R.C.; Haye, R.J. La; Lasnier, C.J.; Maingi, R.; Moyer, R. A.; Schaffer, M. J.; Stangeby, P. G.; Watkins, J.G.; West, W.P.; Whyte, D.G.; Wolf, N. S.

doi:10.1088/0029-5515/42/1/308

Cited by 59 publications

(49 citation statements)

References 24 publications

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“…In the neutral penetration model [22,37,38] the density pedestal width is defined as |R top.ne -R sep , Te | , as given in Figure (4d corroborating evidence that the temperature pedestal width does not scale with ρ * whereas the density pedestal width shows an altogether more complex dynamics for which an explanation may be found through the role of neutral penetration.…”

Section: Experimental Methods and Analysismentioning

confidence: 53%

“…Experiments in support of this model have been presented in the literature, e.g. [22,23], whereas other reports show no variation of Δn ped with 1/n ped , e.g. [24,25,26,27].…”

Section: A Number Of Theoretical Arguments Have Been Made As To What mentioning

confidence: 61%

“…A simple model that incorporates the role of neutral particles on the pedestal structure is given by [22]. This model describes the density pedestal width Δn ped as a function of the neutral mean free path λ n-free into the plasma leading to the simple relation Δn ped ҃λ n-free ҃ 1/n ped .…”

Section: A Number Of Theoretical Arguments Have Been Made As To What mentioning

confidence: 99%

See 2 more Smart Citations

H-mode pedestal scaling in DIII-D, ASDEX Upgrade, and JET

Beurskens¹,

Osborne²,

Schneider

et al. 2011

Physics of Plasmas

122

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Section: Experimental Methods and Analysismentioning

confidence: 53%

“…Experiments in support of this model have been presented in the literature, e.g. [22,23], whereas other reports show no variation of Δn ped with 1/n ped , e.g. [24,25,26,27].…”

Section: A Number Of Theoretical Arguments Have Been Made As To What mentioning

confidence: 61%

Section: A Number Of Theoretical Arguments Have Been Made As To What mentioning

confidence: 99%

See 1 more Smart Citation

H-mode pedestal scaling in DIII-D, ASDEX Upgrade, and JET

Beurskens¹,

Osborne²,

Schneider

et al. 2011

Physics of Plasmas

122

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show abstract

“…Pedestal densities as high as 90% of the Greenwald limit, with no confinement degradation, have been achieved in DIII-D [463] and in type-II ELMy discharges in ASDEX Upgrade [469]. This has been exceeded in JET with highly shaped discharges, in which pedestal densities up to n ped /n Green =1 have been reached [470].…”

Section: Fig 427-2 Modelled Diii-d Density Profiles Normalised Tmentioning

confidence: 99%

“…Ideally, in a burning plasma the separatrix density should be regulated at a value corresponding to the maximum divertor heat dissipation and particle exhaust, while the core and pedestal plasma densities should be optimised for the optimum core performance. However, through anomalous transport, particularly in H-modes [22], and edge ionisation physics, the separatrix density is tightly coupled to the pedestal density [461,462,463], which constitutes a major fraction of the line average density in H-modes (see Sect.…”

Section: Separatrix Densitymentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

Self Cite

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Abstract.Progress, since the ITER Physics Basis publication, in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Experimental areas where significant progress has taken place are : energy transport in the SOL in particular of the anomalous transport scaling, particle transport in the SOL that plays a major role in the interaction of diverted plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism for the ELM energy from the main plasma to the plasma facing components, the physics of plasma detachment and neutral dynamics including the edge density profile structure and the control of plasma particle content and He removal, the erosion of low and high Z materials in fusion devices, their transport to the core plasma and their migration at the plasma edge including the formation of mixed materials, the processes determining the size and location of the retention of tritium in fusion devices and methods to remove it and the processes determining the efficiency of the various fuelling methods as well as their development towards the ITER requirements. This experimental progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction and the further validation of these models by comparing their predictions with the new experimental results. Progress in the modelling development and validation has been mostly concentrated in the following areas : refinement of the predictions for ITER with plasma edge modelling codes by inclusion of detailed geometrical features of the divertor and the introduction of physical effects, which can play a 2 major role in determining the divertor parameters at the divertor for ITER conditions such as hydrogen radiation transport and neutral-neutral collisions, modelling of the ion orbits at the plasma edge, which can play a role in determining power deposition at the divertor target, models for plasma-materials and plasma dynamics interaction during ELMs and disruptions, models for the transport of impurities at the plasma edge to describe the core contamination by impurities and the migration of eroded materials at the edge plasma and its associated tritium retention and models for the turbulent processes that determine the anomalous transport of energy and particles across the SOL. The implications for the expected performance of the reference regimes in ITER, the operation of the ITER device and the lifetime of the plasma facing materials are discussed. Introduction.This chapter outlines the significant progress achieved since the ITER Physics Basis in understanding basic scrape-off layer (SOL) and divertor processes in a tokamak. The interaction of plasma with first-wall surfaces will have considerable impact on the performance of fusion plasmas, the lifetime of plasma facing components, and the retention of tritium in next step Burning Plasma E...

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Influence of flow shear on localized Rayleigh–Taylor and resistive drift wave instabilities

Zhang

Krasheninnikov

Smolyakov

2019

Contributions to Plasma Physics

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The impact of velocity shear on the localized solutions of Rayleigh-Taylor (RT) and resistive drift wave (DW) instabilities has been investigated. The slab geometry is used and the plasma density gradient is assumed to have a finite spatial structure. It demonstrates that the velocity shear has quite different effects on these instabilities: whereas it stabilizes RT instability and causes tilting of the eddies of equipotential contour, it makes a very mild impact on the resistive DW instability and simply shifts the eddies with no tilting.

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High performance H mode plasmas at densities above the Greenwald limit

Cited by 59 publications

References 24 publications

H-mode pedestal scaling in DIII-D, ASDEX Upgrade, and JET

H-mode pedestal scaling in DIII-D, ASDEX Upgrade, and JET

Chapter 4: Power and particle control

Influence of flow shear on localized Rayleigh–Taylor and resistive drift wave instabilities

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