Scrape-off layer properties of ITER-like limiter start-up plasmas in JET

被引:43
|
作者
Arnoux, G. [1 ,2 ]
Farley, T. [1 ,3 ]
Silva, C. [1 ,4 ]
Devaux, S. [1 ,5 ]
Firdaouss, M. [1 ,6 ]
Frigione, D. [1 ,7 ]
Goldston, R. J. [1 ,8 ]
Gunn, J. [1 ,6 ]
Horacek, J. [1 ,9 ]
Jachmich, S. [1 ,10 ]
Lomas, P. J. [1 ,2 ]
Marsen, S. [1 ,11 ]
Matthews, G. F. [1 ,2 ]
Pitts, R. A. [1 ,12 ]
Stamp, M. [1 ,2 ]
Stangeby, P. C. [1 ,13 ]
机构
[1] Culham Sci Ctr, JET EFDA, Abingdon OX14 3DB, Oxon, England
[2] Culham Sci Ctr, EURATOM CCFE Fus Assoc, Abingdon OX14 3DB, Oxon, England
[3] Univ Bristol, HH Wills Phys Lab, Bristol BS8 1TL, Avon, England
[4] Inst Super Tecn, Inst Plasmas & Fusao Nucl, Assoc EURATOM IST, P-1049001 Lisbon, Portugal
[5] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
[6] CEA DSM IRFM, Assoc EURATOM CEA, F-13108 Cadarache, St Paul Lez Dur, France
[7] CR Frascati, Assoc EURATOM ENEA Fus, Rome, Italy
[8] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[9] Inst Plasma Phys AS CR, Assoc EURATOM IPP CR, Prague 18221 8, Czech Republic
[10] Ecole Royale Mil, Assoc EURATOM Belgian State Lab Plasma Phys, B-1000 Brussels, Belgium
[11] EURATOM, Teilinst Greifswald, Max Planck Inst Plasmaphys, D-17491 Greifswald, Germany
[12] ITER Org, F-13115 St Paul Les Durance, France
[13] Univ Toronto, Inst Aerosp Studies, Toronto, ON M3H 5T6, Canada
基金
英国工程与自然科学研究理事会;
关键词
THERMOGRAPHY; TRANSPORT; DIVERTOR; TOKAMAK; FLUXES; POWER; LOAD;
D O I
10.1088/0029-5515/53/7/073016
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
Recent experiments at JET combining reciprocating probe measurements upstream and infrared thermography at the plasma-facing components (PFC) on plasmas in limiter configurations show that the common approach to predicting the power load on the limiter underestimates the heat flux at the contact point by a factor 1.5-3. The current model and scaling laws used for predicting the power load onto the first wall during limiter current ramp-up/down in ITER are uncertain and a better understanding of the heat transport to the PFCs is required. The heat loads on PFCs are usually predicted by projecting the parallel heat flux associated with scrape-off layer (SOL) properties at the outer mid-plane (upstream) along the magnetic field lines to the limiter surface and deducing the surface heat flux through a cosine law, thus ignoring any local effect of the PFC on transport within the SOL. The underestimate of the heat flux is systematic in inner wall limiter configurations, independent of the plasma parameters, whereas in outer limiter configuration this is not observed, probably because of the much shorter SOL power decay length. Models that can explain this enhanced heat flux around the contact point are proposed and discussed although no definitive conclusion can be drawn.
引用
收藏
页数:12
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