ELM mitigation by nitrogen seeding in the JET gas box divertor

被引:47
作者
Rapp, J
Eich, T
von Hellermann, M
Herrmann, A
Ingesson, LC
Jachmich, S
Matthews, GF
Philipps, V
Saibene, G
机构
[1] Forschungszentrum Julich, EURATOM Assoc, TEC,Inst Plasmaphys, D-52425 Julich, Germany
[2] EURATOM, FOM, TEC, Inst Plasmafys Rijnhuizen, NL-3439 MN Nieuwegein, Netherlands
[3] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
[4] EURATOM, Belgian State Assoc, TEC, KMS,ERM,LPP, Brussels, Belgium
[5] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[6] CSU Garching, EFDA, Garching, Germany
关键词
D O I
10.1088/0741-3335/44/6/302
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
One of the most severe problems for fusion reactors is the power load on the divertor target plates. Technically only power loads of less than 10 MW m(-2) are acceptable. However, strong edge localized mode (ELM) activity can lead to power loads in excess of 800 MW m-2. In order to reduce the steady-state heat flux and the transient heat flux due to ELMS, radiation cooling experiments were performed at JET Nitrogen was puffed into the divertor up to a radiative power fraction of 90%. This was achieved at a density of 0.85 times the Greenwald density (Greenwald M 1988 Nucl. Fusion 28 2199), while maintaining an H-factor of f(H98) = 0.82. The Z(eff) in all those discharges stayed around 2.0. At approximately 55% radiative power fraction, the ELM characteristic changes from type I to type III, resulting in a loss of confinement of about 25% due to a degradation of the edge pedestal and hence a reduction of the ELM power load to the divertor tiles. By increasing the radiative power fraction to values of about 90%, the heat flux is reduced to 2 MW m(-2).
引用
收藏
页码:639 / 652
页数:14
相关论文
共 16 条
[1]  
Aymar R, 2001, SUMMARY ITER FINAL D
[2]   The physics of the International Thermonuclear Experimental Reactor FEAT [J].
Campbell, DJ .
PHYSICS OF PLASMAS, 2001, 8 (05) :2041-2049
[3]  
EICH T, 2001, P 28 EUR PHYS SOC A, V25, P1809
[4]   Loss of confinement due to reduction of the edge pedestal in JET [J].
Fishpool, GM .
NUCLEAR FUSION, 1998, 38 (09) :1373-1380
[5]   A NEW LOOK AT DENSITY LIMITS IN TOKAMAKS [J].
GREENWALD, M ;
TERRY, JL ;
WOLFE, SM ;
EJIMA, S ;
BELL, MG ;
KAYE, SM ;
NEILSON, GH .
NUCLEAR FUSION, 1988, 28 (12) :2199-2207
[6]   ENERGY FLUX TO THE ASDEX-UPGRADE DIVERTOR PLATES DETERMINED BY THERMOGRAPHY AND CALORIMETRY [J].
HERRMANN, A ;
JUNKER, W ;
GUNTHER, K ;
BOSCH, S ;
KAUFMANN, M ;
NEUHAUSER, J ;
PAUTASSO, G ;
RICHTER, T ;
SCHNEIDER, R .
PLASMA PHYSICS AND CONTROLLED FUSION, 1995, 37 (01) :17-29
[7]  
INGESSON LC, 1997, CONTROLLED FUSIO A 1, V21, P113
[8]   Plasma detachment in JET Mark I divertor experiments [J].
Loarte, A ;
Monk, RD ;
Martin-Solis, JR ;
Campbell, DJ ;
Chankin, AV ;
Clement, S ;
Davies, SJ ;
Ehrenberg, J ;
Erents, SK ;
Guo, HY ;
Harbour, PJ ;
Horton, LD ;
Ingesson, LC ;
Jackel, H ;
Lingertat, J ;
Lowry, CG ;
Maggi, CF ;
Matthews, GF ;
McCormick, K ;
O'Brien, DP ;
Reichle, R ;
Saibene, G ;
Smith, RJ ;
Stamp, MF ;
Stork, D ;
Vlases, GC .
NUCLEAR FUSION, 1998, 38 (03) :331-371
[9]  
LOARTE A, 2000, 18 IAEA C SORR IT 4
[10]   Studies in JET diverters of varied geometry. II: Impurity seeded plasmas [J].
Matthews, GF ;
Balet, B ;
Cordey, JG ;
Davies, SJ ;
Fishpool, GM ;
Guo, HY ;
Horton, LD ;
von Hellermann, MG ;
Ingesson, LC ;
Lingertat, J ;
Loarte, A ;
McCracken, GM ;
Maggi, CF ;
Monk, RD ;
Parail, VV ;
Reichle, R ;
Stamp, MF ;
Stangeby, PC ;
Stork, D ;
Taroni, A ;
Vlases, GC ;
Zastrow, KD .
NUCLEAR FUSION, 1999, 39 (01) :19-40