EDGE2D modelling of edge profiles obtained in JET diagnostic optimized configuration

Kallenbach, A.; Andrew, Y.; Beurskens, M.; Corrigan, G.; Eich, T.; Jachmich, S.; Kempenaars, M.; Korotkov, A.; Loarte, A.; Matthews, G. F.; Monier‐Garbet, P.; Saibene, G.; Spence, James; Suttrop, W.; Contributors, Jet

doi:10.1088/0741-3335/46/3/001

Cited by 65 publications

(95 citation statements)

References 29 publications

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“…4.2.1-1 [21]. Interpreting this as a contribution from hot ions, it was inferred [22,23] that the energy of D + ions striking the outer target was ~ 300 eV at ν i * ~ 1, consistent with CXRS measurement of separatrix ion temperature. The ion heat flux (derived from the difference in the TC and LP profiles) was closely correlated with a narrow peak in the outer profile [24].…”

Section: 12)mentioning

confidence: 79%

“…An interpretive version of the 2-D fluid code B2-SOLPS5.0 [35] has been used ( [36]) to develop a multi-variable, power law regression scaling for D ⊥ and χ ⊥ in ASDEX-Upgrade by fitting the inter-ELM experimental data, whilst adjusting constant D ⊥ and χ ⊥ values separately. A similar approach was employed for JET data [22] using the EDGE2D/NIMBUS package [37] to match target profiles. In this study, radially piece-wise constant D ⊥ and χ ⊥ were assumed; for the outer core, the edge transport barrier (ETB) and the SOL, with a radial pinch velocity being invoked (typically, inward in the ETB region and outward in the SOL) to match the upstream n e and T e profiles.…”

Section: Figure 421-2 Peak Total (Tc) Q Tot and Electron (Lp) Q mentioning

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%

“…Secondly, there is no experimental evidence that radial gradients in the SOL can be steeper than those just inside the separatrix [505,22] (see also sections 4.2.1.1 and 4.2.7), which are determined, apparently, by stability. The gradients limiting the plasma stability just inside the separatrix can, therefore, be taken as constraints also for the radial gradients in the SOL.…”

Section: Model Parametersmentioning

confidence: 99%

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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: 12)mentioning

confidence: 79%

Section: Figure 421-2 Peak Total (Tc) Q Tot and Electron (Lp) Q mentioning

confidence: 99%

Section: Separatrix Densitymentioning

confidence: 99%

Section: Model Parametersmentioning

confidence: 99%

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Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…The amount of gas puff in the calculations is adjusted so as to be equal to the pumped flux derived from ionisation gauge measurements in the pump chamber and the known pumping speed [9]. Only conditions are taken into account where the pumped flux is close to the puffed flux, corresponding to small net wall pumping or gas release.…”

Section: Particle Transport Calculationsmentioning

confidence: 99%

Spectroscopic investigation of carbon migration with tungsten walls in ASDEX Upgrade

Kallenbach

Dux

Harhausen

et al. 2007

Journal of Nuclear Materials

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Spectroscopic measurements of carbon fluxes in the mainly tungsten-coated ASDEX Upgrade tokamak are analysed with a particle transport and migration code. The transport parameters for deuterium and carbon are calibrated against flux measurements for different experimental conditions. Additional information is obtained from the re-appearance time of carbon after a boronization. The code reproduces the experimental finding that despite a 85 % (2006 campaign) tungsten coverage of the primary PFCs, the carbon concentration in the core and edge plasma is reduced by about a factor 2 only compared to full carbon PFCs. This behaviour is explained by the strong main chamber recycling of carbon in comparison with the loss flux to the inner divertor. The quick recovery of the carbon level in the plasma after a boronisation is explained by carbon influx from the outer divertor.

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