The 'Hybird' scenario in JET: towards its validation for ITER

被引:97
作者
Joffrin, E [1 ]
Sips, ACC
Artaud, JF
Becoulet, A
Bertalot, L
Budny, R
Buratti, P
Belo, P
Challis, CD
Crisanti, F
de Baar, M
de Vires, P
Gormezano, C
Giroud, C
Gruber, O
Huysmans, GTA
Imbeaux, F
Isayama, A
Litaudon, X
Lomas, PJ
McDonald, DC
Na, YS
Pinches, SD
Staebler, A
Tala, T
Tuccillo, A
Zastrow, KD
机构
[1] EURATOM, CEA, DSM, DRFC, F-13108 Cadarache, France
[2] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
[3] EURATOM, ENEA, Frascati, Italy
[4] Princeton Univ, Plasma Phys Lab, Princeton, NJ USA
[5] Inst Super Tecn, P-1049001 Lisbon, Portugal
[6] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[7] EURATOM, FOM, TEC, FOM Rijnhuizen, NL-3430 BE Nieuwegein, Netherlands
[8] Japan Atom Res Inst, Naka, Ibaraki 3110193, Japan
[9] Korea Basic Sci Inst, Taejon 305333, South Korea
[10] EURATOM, TEKES, VTT Proc, FIN-02044 Espoo, Finland
关键词
D O I
10.1088/0029-5515/45/7/010
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
In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to beta(N) = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (rho*) corresponding to identical ASDEX Upgrade discharges. Stationary conditions have been achieved with the fusion figure of merit (H(89).beta(N)/q(95)(2)) reaching 0.42 at q(95) = 3.9. The JET discharges show similar MHD, edge and current profile behaviour, when compared with the ASDEX Upgrade. In addition, the JET experiments have extended the hybrid scenario operation at higher toroidal field of 2.4 T and lower rho* towards the projected ITER values. Using this database, transport and confinement properties are characterized with respect to the standard H-mode regime. Moreover, trace tritium has been injected to assess the diffusion and convective coefficients of the fusion fuel. The maximization of confinement and stability properties provides, to this scenario, a good probability of achieving a high fusion gain at reduced plasma current for durations of up to 2000 s in ITER.
引用
收藏
页码:626 / 634
页数:9
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