Confinement properties of high density impurity seeded ELMy H-mode discharges at low and high triangularity on JET

Dumortier, P.; Andrew, P.; Bonheure, G.; Budny, R.; Buttery, R. J.; Charlet, M.; Coffey, I.; Baar, M. de; Vries, P. C. de; Eich, T.; Hillis, D.L.; Ingesson, C.; Jachmich, S.; Jackson, G.L.; Kallenbach, A.; Koslowski, H. R.; Lawson, K.; Liu, C.; Maddison, G.; Messiaen, A.; Monier‐Garbet, P.; Murakami, M.; Nave, M. F. F.; Ongena, J.; Parail, V.; Puiatti, M. E.; Rapp, J.; Sartori, F.; Stamp, M.; Strachan, J.; Suttrop, W.; Telesca, G.; Tokar, M. Z.; Unterberg, B.; Valisa, M.; Hellermann, M. von; Weyssow, Boris

doi:10.1088/0741-3335/44/9/304

Cited by 49 publications

(35 citation statements)

References 19 publications

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“…The high triangularity allows to operate at higher density without sacrifice in confinement. This has been first shown in deuterium seeded type-I ELMy H-modes [21,22] and impurity seeded type-I ELMy H-modes [23]. This results in an increase in the product N GW × H 98(y,2) by approximately 20%.…”

Section: Confinement Scalingmentioning

confidence: 69%

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Rapp¹,

Corre²,

Andrew³

et al. 2009

Nucl. Fusion

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One of the most severe problems for fusion reactors is the power load on the plasma facing components. The challenge is to develop operation scenarios, which combine sufficient energy confinement with benign heat loads to the plasma facing components. The radiative type-III ELMy H-mode seems a possible solution for such an integrated ITER scenario. Nitrogen seeded type-III ELMy H-modes for the standard inductive scenario and the high beta stationary hybrid scenario are investigated with respect to their transient and steady-state power fluxes to the divertor, confinement properties, edge operational space, core operational space, plasma purity and MHD behaviour. A large database of highly radiative type-III ELMy H-modes on JET is used for extrapolations to ITER. On this basis the transient heat load should be acceptable for ITER. It was found that the scaling of the confinement time with respect to the ion gyroradius is close to the gyro-Bohm scaling. Scalings with respect to the plasma collisionality suggest that the confinement will be good enough for an ITER scenario at 17 MA with a power amplification factor (Q) of 10 and might be marginally good enough for a Q = 10 scenario at 15 MA. Those extrapolations are supported by simulations with an integrated core/edge model COREDIV. In addition the hybrid scenario with type-III edge localized modes has been proven to have improved edge conditions without any modification of the central plasma current profile, indicating it is compatible with a high beta operation for a steady-state ITER Q = 5 scenario.

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Section: Confinement Scalingmentioning

confidence: 69%

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Rapp¹,

Corre²,

Andrew³

et al. 2009

Nucl. Fusion

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“…The JET Type-I ELM regime described above is an example of simultaneous feedback control of the H-factor and fraction of the radiated power using Ar. Good performance was maintained for 5 seconds with constant neutron yield, formation of a radiating belt and reduction of target plate temperature [135], although, the resulting core argon concentration in such discharges is higher than required for ITER. In ASDEX Upgrade, a new control technique has recently beendeveloped in which simultaneous feedback on the divertor neutral particle flux and electron temperature are combined with external ELM triggering via high field side pellet injection (e.g.…”

Section: Use Of Extrinsic Impurity Radiation To Reduce Divertor Heat mentioning

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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“…The energy confinement in RI-mode scales with lineaveraged density (n e ) as in the linear Ohmic confinement regime; however, the general degradation of confinement with total heating power remains [1]: τ RI ∼n e P −2/3 tot . Recently, improvement of confinement with impurity injection has also been obtained at DIII-D, JET and FTU [3][4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Confinement and transport in EC heated RI-mode discharges in TEXTOR

Hogeweij¹,

Dumortier²,

Eester³

et al. 2004

Nucl. Fusion

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This paper reports on experiments in TEXTOR with electron cyclotron resonance heating (ECRH) of radiatively improved (RI) mode discharges. With ECRH the energy content of RI-mode discharges can be increased without the normally observed power degradation in confinement time. The experiments are described and the effects of ECRH on global confinement and local plasma parameters of RI-mode discharges are discussed; the favourable scaling of energy content is due to a zone of low electron thermal transport just outside the sawtooth inversion radius. Moreover, the heating effect of ECRH in the RI-mode is compared with the effect in L-mode; this comparison sheds some light on the physics of electron thermal transport in RI-mode discharges.

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Confinement properties of high density impurity seeded ELMy H-mode discharges at low and high triangularity on JET

Cited by 49 publications

References 19 publications

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

Chapter 4: Power and particle control

Confinement and transport in EC heated RI-mode discharges in TEXTOR

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