Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges

被引:93
作者
Eich, T. [1 ]
Manz, P. [1 ]
Goldston, R. J. [2 ]
Hennequin, P. [3 ]
David, P. [1 ]
Faitsch, M. [1 ]
Kurzan, B. [1 ]
Sieglin, B. [1 ]
Wolfrum, E. [1 ]
机构
[1] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany
[2] Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA
[3] Ecole Polytech, LPP, CNRS, F-91128 Palaiseau, France
关键词
power width; turbulence; density limit; H-Mode; tokamak; ASDEX Upgrade; SOL decay length; TOKAMAK EDGE TURBULENCE; SCRAPE-OFF LAYER; DENSITY LIMIT; TRANSPORT;
D O I
10.1088/1741-4326/ab7a66
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Divertor heat flux data from infra red (IR) from various tokamaks in H-Mode regime show that the power width, lambda q<i, scales approximately like 1.6 (R/a) rho(s,pol). However, the IR based scaling comes with the restriction that only discharges were considered with attached divertor conditions. Here we set up a new data base covering low edge density data but also including high density plasmas reaching the H-mode density limit. We use Thomson-scattering to measure the electron temperature decay length which will set the near-SOL power width through parallel heat conduction. We present scaling results for the density, temperature and pressure separatrix fall-off lengths. As the principal result we derive a generalized power width scaling which reads as lambda q proportional to rho s,pol.(1+2.1 alpha t1.7)alpha t<i describes a normalized collisionality (alpha t=3.10-18Rq2nZeffT-2<i). The parameter alpha t alpha(d) introduced by Rogers, Drake and Zeiler (RDZ). The edge operational space for ASDEX Upgrade displays a boundary qualitatively in agreement with the region labelled as density limit in the edge plasma phase space proposed by RDZ. The data base shows in the limit of low edge densities ( alpha t similar or equal to 0.2<i) accurate agreement to the IR based power width scaling. At elevated separatrix densities ( alpha t similar or equal to 1<i) the power width is broadened by a factor of up to about three accompanied by a reduction of the H-98,H-y2 confinement factor. Plasmas with higher triangularity show higher values for H-98,H-y2 in the same range of normalized collisionality.
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页数:13
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共 49 条
[1]   On the scaling of avaloids and turbulence with the average density approaching the density limit [J].
Antar, GY ;
Counsell, G ;
Ahn, JW .
PHYSICS OF PLASMAS, 2005, 12 (08) :1-11
[2]   The H-mode density limit in the full tungsten ASDEX Upgrade tokamak [J].
Bernert, M. ;
Eich, T. ;
Kallenbach, A. ;
Carralero, D. ;
Huber, A. ;
Lang, P. T. ;
Potzel, S. ;
Reimold, F. ;
Schweinzer, J. ;
Viezzer, E. ;
Zohm, H. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2015, 57 (01)
[3]   High-resolution heat flux width measurements at reactor-level magnetic fields and observation of a unified width scaling across confinement regimes in the Alcator C-Mod tokamak [J].
Brunner, D. ;
LaBombard, B. ;
Kuang, A. Q. ;
Terry, J. L. .
NUCLEAR FUSION, 2018, 58 (09)
[4]   Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER [J].
Chang, C. S. ;
Ku, S. ;
Loarte, A. ;
Parail, V. ;
Koechl, F. ;
Romanelli, M. ;
Maingi, R. ;
Ahn, J. -W. ;
Gray, T. ;
Hughes, J. ;
LaBombard, B. ;
Leonard, T. ;
Makowski, M. ;
Terry, J. .
NUCLEAR FUSION, 2017, 57 (11)
[5]   Analysis of equilibrium and turbulent fluxes across the separatrix in a gyrokinetic simulation [J].
Charidakos, I. Keramidas ;
Myra, J. R. ;
Parker, S. ;
Ku, S. ;
Churchill, R. M. ;
Hager, R. ;
Chang, C. S. .
PHYSICS OF PLASMAS, 2018, 25 (07)
[6]   Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths [J].
Chen, B. ;
Xu, X. Q. ;
Xia, T. Y. ;
Li, N. M. ;
Porkolab, M. ;
Edlund, E. ;
LaBombard, B. ;
Terry, J. ;
Hughes, J. W. ;
Ye, M. Y. ;
Wan, Y. X. .
PHYSICS OF PLASMAS, 2018, 25 (05)
[7]   Correlation of the tokamak H-mode density limit with ballooning stability at the separatrix [J].
Eich, T. ;
Goldston, R. J. ;
Kallenbach, A. ;
Sieglin, B. ;
Sun, H. J. ;
Abduallev, S. ;
Abhangi, M. ;
Abreu, P. ;
Afzal, M. ;
Aggarwal, K. M. ;
Ahlgren, T. ;
Ahn, J. H. ;
Aho-Mantila, L. ;
Aiba, N. ;
Airila, M. ;
Albanese, R. ;
Aldred, V. ;
Alegre, D. ;
Alessi, E. ;
Aleynikov, P. ;
Alfier, A. ;
Alkseev, A. ;
Allinson, M. ;
Alper, B. ;
Alves, E. ;
Ambrosino, G. ;
Ambrosino, R. ;
Amicucci, L. ;
Amosov, V. ;
Sunden, E. Andersson ;
Angelone, M. ;
Anghel, M. ;
Angioni, C. ;
Appel, L. ;
Appelbee, C. ;
Arena, P. ;
Ariola, M. ;
Arnichand, H. ;
Arshad, S. ;
Ash, A. ;
Ashikawa, N. ;
Aslanyan, V. ;
Asunta, O. ;
Auriemma, F. ;
Austin, Y. ;
Avotina, L. ;
Axton, M. D. ;
Ayres, C. ;
Bacharis, M. ;
Baciero, A. .
NUCLEAR FUSION, 2018, 58 (03)
[8]   Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER [J].
Eich, T. ;
Leonard, A. W. ;
Pitts, R. A. ;
Fundamenski, W. ;
Goldston, R. J. ;
Gray, T. K. ;
Herrmann, A. ;
Kirk, A. ;
Kallenbach, A. ;
Kardaun, O. ;
Kukushkin, A. S. ;
LaBombard, B. ;
Maingi, R. ;
Makowski, M. A. ;
Scarabosio, A. ;
Sieglin, B. ;
Terry, J. ;
Thornton, A. .
NUCLEAR FUSION, 2013, 53 (09)
[9]   Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model [J].
Eich, T. ;
Sieglin, B. ;
Scarabosio, A. ;
Fundamenski, W. ;
Goldston, R. J. ;
Herrmann, A. .
PHYSICAL REVIEW LETTERS, 2011, 107 (21)
[10]   Change of the scrape-off layer power width with the toroidal B-field direction in ASDEX upgrade [J].
Faitsch, M. ;
Sieglin, B. ;
Eich, T. ;
Sun, H. J. ;
Herrmann, A. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2015, 57 (07)