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Journal Articles

Discrepancy between modelled and measured radial electric fields in the scrape-off layer of divertor tokamaks; A Challenge for 2D fluid codes?

Chankin, A. V.*; Coster, D. P.*; Asakura, Nobuyuki; Bonnin, X.*; Conway, G. D.*; Corrigan, G.*; Erents, S. K.*; Fundamenski, W.*; Horacek, J.*; Kallenbach, A.*; et al.

Nuclear Fusion, 47(5), p.479 - 489, 2007/05

 Times Cited Count:30 Percentile:73.38(Physics, Fluids & Plasmas)

Radial electric field in known to be one of the drivers for the parallel ion flow in the SOL. It contributes to the ion Pfirsch-Schluter flow and determines the return parallel flow compensating poloidal ExB drift. It was established recently that 2D fluid codes EDGE2D and SOLPS underestimate the predicted Er in the SOL compared to experimentally measured values. The present work demonstrates that this underestimate can be responsible for the large discrepancy between measured and simulated parallel ion flows in the SOL. Provided radial electric field was modelled correctly by the codes, an increase in the predicted Mach number of the parallel ion flow by up to a factor 3 for the JET could be expected. This would entirely eliminate the difference between the experimentally determined part of the ion flow that depends on the toroidal field direction, and the modelled ion flow attributed to drifts. Discrepancy between measured and simulated flows in ASDEX-Upgrade was also reduced.

Journal Articles

Plasma-surface interaction, scrape-off layer and divertor physics; Implications for ITER

Lipschultz, B.*; Asakura, Nobuyuki; Bonnin, X.*; Coster, D. P.*; Counsell, G.*; Doerner, R.*; Dux, R.*; Federici, G.*; Fenstermacher, M. E.*; Fundamenski, W.*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

The work of the ITPA SOL/divertor group is reviewed. The high-n nature of ELMs has been elucidated and new measurements have determined that they carry 10-20% of the ELM energy to the far SOL with implications for ITER limiters and the upper divertor. Analysis of ELM measurements imply that the ELM continuously loses energy as it travels across the SOL. The prediction of ITER divertor disruption power loads have been reduced as a result of finding that the divertor footprint broadens during the thermal quench and that the plasma can lose up to 80% of its thermal energy before the thermal quench (not for VDEs or ITBs). Disruption mitigation through massive gas puffing has been successful at reducing divertor heat loads but estimates of the effect on the main chamber walls indicate 10s of kG of Be would be melted/mitigation. Long-pulse studies have shown that the fraction of injected gas that can be recovered after a discharge decreases with discharge length. The use of mixed materials gives rise to a number of potential processes.

Oral presentation

Simulation of double-null divertor on JT-60SA

Suzuki, Yutaka; Kawashima, Hisato; Coster, D. P.*; Sakurai, Shinji; Matsukawa, Makoto; Tamai, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Divertor simulation on JT-60SA, 2

Suzuki, Yutaka; Kawashima, Hisato; Coster, D. P.*; Sakurai, Shinji; Matsukawa, Makoto; Tamai, Hiroshi

no journal, , 

no abstracts in English

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