Integrated modelling of the current profile in steady-state and hybrid ITER scenarios

被引:47
作者
Houlberg, WA [1 ]
Gormezano, C
Artaud, JF
Barbato, E
Basiuk, V
Becoulet, A
Bonoli, P
Budny, RV
Eriksson, LG
Farina, D
Gribov, Y
Harvey, RW
Hobirk, J
Imbeaux, F
Kessel, CE
St John, H
Volpe, F
Westerhof, E
Zvonkov, A
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[2] ENEA Fusione, CR, EURATOM Assoc, Frascati, Italy
[3] MIT, Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA
[4] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[5] CNR, IFP, ENEA, EURATOM Assoc, Milan, Italy
[6] ITER Int Team, Naka Joint Work Site, Naka, Ibaraki, Japan
[7] CompX, Del Mar, CA USA
[8] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
[9] RRC, Kurchatov Inst, Nucl Fus Inst, Moscow 123128, Russia
[10] Gen Atom Co, San Diego, CA USA
[11] EURATOM, UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon, Oxon, England
关键词
D O I
10.1088/0029-5515/45/11/012
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
We present integrated modelling of steady-state and hybrid scenarios for ITER parameters using several predictive transport codes. These employ models for non-inductive current drive sources in conjunction with various theory-based and semi-empirical transport models. In conjunction with the simulation effort, the current drive models are being evaluated in a series of cross-code and code-experiment comparisons under ITER-relevant conditions. New benchmark evaluations of current drive from injection of neutral beams (NBCD), electron cyclotron waves (ECCD) and lower hybrid waves (LHCD) are reported. Simulations using several transport modelling codes self-consistently calculate the heating and current drive sources using ITER design parameters. Operating constraints are also taken into account, although the calculations reported here still require further refinement. The modelling addresses both the final stationary state and dynamic access to it. The simulations indicate that generation and control of internal and edge barriers to access and maintain high confinement will be a major undertaking for future simulations, as well as a challenge for the ITER steady-state and hybrid experimental programme.
引用
收藏
页码:1309 / 1320
页数:12
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