ELM energy and particle losses and their extrapolation to burning plasma experiments

Loarte, A.; Saibene, G.; Sartori, R.; Bécoulet, M.; Horton, L.D.; Eich, T.; Herrmann, A.; Laux, M.; Matthews, G. F.; Jachmich, S.; Asakura, N.; Chankin, A.; Leonard, A.W.; Porter, G. D.; Federici, G.; Shimada, M.; Sugihara, M.; Janeschitz, G.

doi:10.1016/s0022-3115(02)01398-3

Cited by 134 publications

(127 citation statements)

References 8 publications

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“…As the pedestal density/collisionality is increased, the energy deposited in the divertor varies from short timescales, dominated by conduction, to longer timescales, dominated by convection [165,163,31].…”

Section: Mechanism Of Type I Elm Energy Transport To Pfcsmentioning

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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Section: Mechanism Of Type I Elm Energy Transport To Pfcsmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…The standard tokamak H-mode, which is foreseen as the ITER baseline operating scenario, is characterised by a steep plasma pressure gradient and associated increased current density at the edge transport barrier which exceeds a threshold value to drive magnetohydrodynamic (MHD) instabilities referred to as Edge Localized Modes (ELMs) [1]. Active control of ELMs by resonant magnetic perturbation (RMP) fields offers an attractive method for ITER.…”

Section: Introductionmentioning

confidence: 99%

Overview of ELM Control by Low n Magnetic Perturbations on JET

Liang

Koslowski

Jachmich

et al. 2010

Plasma and Fusion Research

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A series of ELM control experiments have been performed on JET aiming at a better understanding of the plasma response to applied magnetic perturbations. The dynamics of the edge profiles with applied n = 1 fields have been studied in the type-I ELM H-mode plasmas. Typically, the pedestal density decreased by about 20 % when the n = 1 perturbation field was applied (So called pump-out effect). However, there is no influence of the n = 1 fields on the recovery rate of the pedestal pressure, but the ELM crash occurs earlier and at a lower level of the pedestal pressure and pressure gradient. The compensation of the density pump-out has been demonstrated using either gas fuelling or pellets injection in low triangularity H-mode plasmas. Strong toroidal rotation braking by more than 60 % has been observed, and found to be independent on the safety factor. The calculated Neoclassical Toroidal Viscosity (NTV) torque profile in the ν regime including the boundary effect is in agreement with the observed torque profile induced by the n = 1 fields on JET. No complete ELM suppression was observed by application of either n = 1 or n = 2 fields with a Chirikov parameter above one at √ Ψ ≥ 0.925, which is one of the important criteria for the design of ITER ELM control coils.

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“…The Type I ELM typically results in larger heat pulses than other ELM types 2 . Such transient PFC loading is tolerable in present day machines, but extrapolations show that severe PFC damage may occur in larger, higher power density machines (such as ITER) when the ELM power loading exceeds material limits.…”

Section: Introductionmentioning

confidence: 99%

ELMs and the H-mode Pedestal in NSTX

Maingi

Sabbagh

Bush

et al. 2004

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We report on the behavior of ELMs in NBI-heated H-mode plasmas in NSTX. It is observed that the size of Type I ELMs, characterized by the change in plasma energy, decreases with increasing density, as observed at conventional aspect ratio. It is also observed that the Type I ELM size decreases as the plasma equilibrium is shifted from a symmetric double-null toward a lower single-null configuration. Type III ELMs have also been observed in NSTX, as well as a high-performance regime with small ELMs which we designate Type V. These Type V ELMs are consistent with high bootstrap current operation and density approaching Greenwald scaling. The Type V ELMs are characterized by an intermittent n=1 MHD mode rotating counter to the plasma current. Without active pumping, the density rises continuously through the Type V phase. However, efficient in-vessel pumping should allow density control, based on particle containment time estimates.

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ELM energy and particle losses and their extrapolation to burning plasma experiments

Cited by 134 publications

References 8 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Overview of ELM Control by Low n Magnetic Perturbations on JET

ELMs and the H-mode Pedestal in NSTX

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