Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

被引:534
作者
Eich, T. [1 ]
Leonard, A. W. [2 ]
Pitts, R. A. [3 ]
Fundamenski, W. [4 ]
Goldston, R. J. [5 ]
Gray, T. K. [6 ]
Herrmann, A. [1 ]
Kirk, A. [4 ]
Kallenbach, A. [1 ]
Kardaun, O. [1 ]
Kukushkin, A. S. [3 ]
LaBombard, B. [7 ]
Maingi, R. [5 ,6 ]
Makowski, M. A. [8 ]
Scarabosio, A. [1 ]
Sieglin, B. [1 ]
Terry, J. [7 ]
Thornton, A. [4 ]
机构
[1] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[2] Gen Atom, San Diego, CA 92186 USA
[3] ITER Org, F-13115 St Paul Les Durance, France
[4] EURATOM, Culham Sci Ctr, CCFE, Abingdon, Oxon, England
[5] Princeton Univ, Plasma Phys Lab, Princeton, NJ 08543 USA
[6] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[7] MIT, Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA
[8] Lawrence Livermore Natl Lab, Livermore, CA 94551 USA
关键词
ALCATOR C-MOD; HEAT-FLUX; JET; FLUCTUATIONS; TRANSPORT; ASDEX;
D O I
10.1088/0029-5515/53/9/093031
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
Amulti-machine database for the H-mode scrape-off layer power fall-off length, lambda(q) in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices of the International Tokamak Physics Activity. Regression inside the database finds that the most important scaling parameter is the poloidal magnetic field (or equivalently the plasma current), with lambda(q) decreasing linearly with increasing B-pol. For the conventional aspect ratio tokamaks, the regression finds lambda(q) alpha B-tor(-0.8). q(95)(1.1).P-SOL(0.1).R-geo(0), yielding lambda(q,) (ITER) congruent to 1mm for the baseline inductive H-mode burning plasma scenario at I-p = 15 MA. The experimental divertor target heat flux profile data, from which lambda(q) is derived, also yield a divertor power spreading factor (S) which, together with lambda(q), allows an integral power decay length on the target to be estimated. There are no differences in the lambda(q) scaling obtained from all-metal or carbon dominated machines and the inclusion of spherical tokamaks has no significant influence on the regression parameters. Comparison of the measured lambda(q) with the values expected from a recently published heuristic drift based model shows satisfactory agreement for all tokamaks.
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页数:7
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共 30 条
[1]   Particle transport in tokamak plasmas, theory and experiment [J].
Angioni, C. ;
Fable, E. ;
Greenwald, M. ;
Maslov, M. ;
Peeters, A. G. ;
Takenaga, H. ;
Weisen, H. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2009, 51 (12)
[2]   Structure and properties of the electrostatic fluctuations in the far scrape-off layer region of Alcator C-Mod [J].
Carreras, BA ;
Lynch, VE ;
LaBombard, B .
PHYSICS OF PLASMAS, 2001, 8 (08) :3702-3707
[3]   ELM resolved energy distribution studies in the JET MKII Gas-Box divertor using infra-red thermography [J].
Eich, T. ;
Andrew, P. ;
Herrmann, A. ;
Fundamenski, W. ;
Loarte, A. ;
Pitts, R. A. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2007, 49 (05) :573-604
[4]   Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET [J].
Eich, T. ;
Sieglin, B. ;
Scarabosio, A. ;
Herrmann, A. ;
Kallenbach, A. ;
Matthews, G. F. ;
Jachmich, S. ;
Brezinsek, S. ;
Rack, M. ;
Goldston, R. J. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S72-S77
[5]   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)
[6]   Multi-parameter scaling of divertor power load profiles in D, H and He plasmas on JET and implications for ITER [J].
Fundamenski, W. ;
Eich, T. ;
Devaux, S. ;
Jachmich, S. ;
Jakubowski, M. ;
Thomsen, H. ;
Arnoux, G. ;
Militello, F. ;
Havlickova, E. ;
Moulton, D. ;
Brezinsek, S. ;
Maddison, G. ;
McCormick, K. ;
Huber, A. .
NUCLEAR FUSION, 2011, 51 (08)
[7]   Fluctuations and transport in the TCV scrape-off layer [J].
Garcia, O. E. ;
Horacek, J. ;
Pitts, R. A. ;
Nielsen, A. H. ;
Fundamenski, W. ;
Naulin, V. ;
Rasmussen, J. Juul .
NUCLEAR FUSION, 2007, 47 (07) :667-676
[8]   Integration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmas [J].
Giroud, C. ;
Maddison, G. ;
McCormick, K. ;
Beurskens, M. N. A. ;
Brezinsek, S. ;
Devaux, S. ;
Eich, T. ;
Frassinetti, L. ;
Fundamenski, W. ;
Groth, M. ;
Huber, A. ;
Jachmich, S. ;
Jarvinen, A. ;
Kallenbach, A. ;
Krieger, K. ;
Moulton, D. ;
Saarelma, S. ;
Thomsen, H. ;
Wiesen, S. ;
Alonso, A. ;
Alper, B. ;
Arnoux, G. ;
Belo, P. ;
Boboc, A. ;
Brett, A. ;
Brix, M. ;
Coffey, I. ;
de la Luna, E. ;
Dodt, D. ;
De Vries, P. ;
Felton, R. ;
Giovanozzi, E. ;
Harling, J. ;
Harting, D. ;
Hawkes, N. ;
Hobirk, J. ;
Jenkins, I. ;
Joffrin, E. ;
Kempenaars, M. ;
Lehnen, M. ;
Loarer, T. ;
Lomas, P. ;
Mailloux, J. ;
McDonald, D. ;
Meigs, A. ;
Morgan, P. ;
Nunes, I. ;
van Thun, C. Perez ;
Riccardo, V. ;
Rimini, F. .
NUCLEAR FUSION, 2012, 52 (06)
[9]   Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks [J].
Goldston, R. J. .
NUCLEAR FUSION, 2012, 52 (01)
[10]   Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX [J].
Gray, T. K. ;
Maingi, R. ;
Soukhanovskii, V. A. ;
Surany, J. E. ;
Ahn, J-W ;
McLean, A. G. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) :S360-S364