Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling

Kukushkin, A.S.; Pacher, H.D.; Pacher, G.W.; Janeschitz, G.; Coster, D.; Loarte, A.; Reiter, D.

doi:10.1088/0029-5515/43/8/312

Cited by 122 publications

(166 citation statements)

References 18 publications

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“…For ITER, predictive computations have been made for the plasma boundary [5], which allow to extract estimates of the spatial distribution of both the fuel and carbon flux components.…”

Section: Extrapolation To Itermentioning

confidence: 99%

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Formation of deuterium–carbon inventories in gaps of plasma facing components

Krieger

Jacob

Rudakov³

et al. 2007

Journal of Nuclear Materials

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Plasma facing components for ITER will be manufactured as macro brush structures or with castellated surfaces. Material samples with gaps of similar geometry as intended for ITER were exposed to different plasma conditions in TEXTOR, DIII-D and ASDEX Upgrade. In all devices a decrease of both carbon and deuterium inventories at the side faces from the gap entrance into the gap with scale-lengths in the mm range is found. The fraction of D retained at the gap surfaces is in the range of 0.4-4% of the incident flux. Main parameters determining the retained D-fraction are the temperature of the respective surfaces and the carbon fraction in the incident flux. Extrapolation of tritium inventory growth rates to ITER dimensions assuming the measured retention fractions at T>200ºC and using a D/T-flux distribution with a carbon fraction of from B2/EIRENE simulations of an ITER H-mode discharge yields 1% ≈ 1 a contribution to the increase of the total in-vessel tritium inventory in the range of 0.5-5g T/discharge.

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“…For ITER, predictive computations have been made for the plasma boundary [5], which allow to extract estimates of the spatial distribution of both the fuel and carbon flux components.…”

Section: Extrapolation To Itermentioning

confidence: 99%

“…Their prediction is a separate task beyond the scope of this paper. For projections to ITER, results from predictive B2/EIRENE plasma simulations [5] will be used.…”

Section: Introductionmentioning

confidence: 99%

Formation of deuterium–carbon inventories in gaps of plasma facing components

Krieger

Jacob

Rudakov³

et al. 2007

Journal of Nuclear Materials

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“…The operational space of the ITER divertor is multi-dimensional [7], where some dimensions represent the engineering parameters (q pk , particle throughput to the pump), some the control parameters (gas puffing rate and pumping speed), and some characterize the interface with the core plasma (power input to the SOL, separatrix density, etc.). Constraints stemming from design limitations and physical considerations delineate an operational window in this operational space.…”

Section: Effect Of the Leaks On Divertor Performancementioning

confidence: 99%

“…Constraints stemming from design limitations and physical considerations delineate an operational window in this operational space. A detailed study of the operational space of the ITER divertor was presented in [7], although with a simplified, linear model of the neutral particle transport.…”

Section: Effect Of the Leaks On Divertor Performancementioning

confidence: 99%

Effect of conditions for gas recirculation on divertor operation in ITER

et al. 2007

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Abstract. The latest results of B2-Eirene modelling of ITER divertor operation are presented.The operational window is further explored with an improved model of the neutral transport, the effect of gas leaks between the divertor cassettes is assessed, and the sensitivity of the results to features of the divertor geometry and to the gas puffing arrangement is analysed.The presence of neutral-neutral collisions in the model makes the results rather insensitive to the detail of the divertor shape. The analysis shows that the effect of the gas leak on the divertor performance in ITER is weak and therefore inter-cassette sealing may be not critical.

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“…For Tungsten, at least in the D-T campaign the foreseen ITER divertor target material, the power load must be kept below P = 5 MW/m 2 in continuous operation. This can in ITER only be achieved with the plasma being detached or partially detached [1,2].…”

Section: Introductionmentioning

confidence: 99%

Characterization of the fluctuating detachment state in ASDEX Upgrade

Potzel

Wischmeier

Bernert

et al. 2013

Journal of Nuclear Materials

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In this article we present experimental investigations of divertor detachment in ASDEX Upgrade. For this purpose we performed a series of ohmic and LMode density ramp discharges. The electron density in the divertor volume is determined with a spectroscopic measurement of the Stark broadened line shape of the D line. These measurements are combined with several other diagnostics, yielding a consistent picture of detachment. It will be shown that detachment in ASDEX Upgrade is not a continuously evolving process but can be divided into three different states. Within these states, the conditions in the inner and outer divertor are strongly coupled. Radiative fluctuations, measured with fast diode bolometers, combined with a region of high electron density appear at the X-point during one of these states. We show how N 2 seeding during this state alters the divertor conditions. Finally an unstable situation was found, where the divertor plasma oscillates between two detachment states.

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Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling

Cited by 122 publications

References 18 publications

Formation of deuterium–carbon inventories in gaps of plasma facing components

Formation of deuterium–carbon inventories in gaps of plasma facing components

Effect of conditions for gas recirculation on divertor operation in ITER

Characterization of the fluctuating detachment state in ASDEX Upgrade

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