Transport of edge localized modes energy and particles into the scrape off layer and divertor of DIII-D

Leonard, A.W.; Osborne, T.H.; Fenstermacher, M.E.; Groebner, R. J.; Groth, M.; Lasnier, C.J.; Mahdavi, M. A.; Pétrie, T.W.; Snyder, P. B.; Watkins, J.G.; Zeng, L.

doi:10.1063/1.1567723

Cited by 58 publications

(72 citation statements)

References 15 publications

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“…Previous measurements [58] confirmed the expected outer midplane dominated peeling-ballooning spatial structure at ELM onset. A reduction of n e ped was seen at all densities during an ELM and T e ped was also reduced at low n e ped ("conductive" ELMs) but no change to T e ped was seen during ELMs at high density ("convective" ELMs) [59,60]. Scanning reflectometer data show that the particles lost from the pedestal during an ELM appear far out in the SOL at the midplane [61,62].…”

Section: Elm Dynamics In the Pedestal And Midplane Solmentioning

confidence: 99%

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

Fenstermacher

Osborne²,

Leonard³

et al. 2005

Nucl. Fusion

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ABSTRACT. Experiments are described that have increased understanding of the transport and stability physics that set the H-mode edge pedestal width and height, determine the onset of Type-I edge localized modes (ELMs), and produce the nonlinear dynamics of the ELM perturbation in the pedestal and scrape-off layer (SOL). Models now exist for the n e pedestal profile and the p e height at the onset of Type-I ELMs, and progress has been made toward models of the T e pedestal width and nonlinear ELM evolution. Similarity experiments between DIII-D and JET suggested that neutral penetration physics plays an important role in the relationship between the width and height of the n e pedestal. Plasma physics appears to dominate in setting the T e pedestal width. Measured pedestal conditions including edge current at ELM onset agree with intermediate-n peeling-ballooning (P-B)

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Section: Elm Dynamics In the Pedestal And Midplane Solmentioning

confidence: 99%

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

Fenstermacher

Osborne²,

Leonard³

et al. 2005

Nucl. Fusion

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“…In an ELM event, the impulsive thermal loads to the divertor can be up to 20% of the H-mode pedestal energy [20]. Because this energy is deposited in a very short time, the divertor plate surface temperature could rise to the melting or sublimation point within a single ELM event.…”

Section: Interaction Of Plasma With the First Wallmentioning

confidence: 99%

Development of burning plasma and advanced scenarios in the DIII-D tokamak

Luce

2005

Nucl. Fusion

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Abstract. Significant progress in the development of burning plasma scenarios, steady-state scenarios at high fusion performance, and basic tokamak physics has been made by the DIII-D Team. Discharges similar to the ITER baseline scenario have demonstrated normalized fusion performance nearly 50% higher than required for Q = 10 in ITER, under stationary conditions. Discharges that extrapolate to Q ~ 10 for longer than one hour in ITER at reduced current have also been demonstrated in DIII-D under stationary conditions. Proof of high fusion performance with full noninductive operation has been obtained. Underlying this work are studies validating approaches to confinement extrapolation, disruption avoidance and mitigation, tritium retention, ELM avoidance, and operation above the no-wall pressure limit. In addition, the unique capabilities of the DIII-D facility have advanced studies of the sawtooth instability with unprecedented time and space resolution, threshold behavior in the electron heat transport, and rotation in plasmas in the absence of external torque.

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“…However, we cannot again rule out that the change of the in/out ELM energy deposition asymmetry is influenced by the ELM energy loss from the main plasma changing from being dominated by conduction to convection (see Sec. 4.2.2.4), or by changes in the peeling-ballooning nature of the ELM trigger [184,186].…”

Section: In/out Elm Energy Flux Asymmetries and Total Divertor Elm Enmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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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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Transport of edge localized modes energy and particles into the scrape off layer and divertor of DIII-D

Cited by 58 publications

References 15 publications

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

Structure, stability and ELM dynamics of the H-mode pedestal in DIII-D

Development of burning plasma and advanced scenarios in the DIII-D tokamak

Chapter 4: Power and particle control

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