CORSICA modelling of ITER hybrid operation scenarios

被引：28

作者：

Kim, S. H. ^{[1
]}

Bulmer, R. H. ^{[2
]}

Campbell, D. J. ^{[1
]}

Casper, T. A. ^{[1
,3
]}

LoDestro, L. L. ^{[2
]}

Meyer, W. H. ^{[2
]}

Pearlstein, L. D. ^{[2
]}

Snipes, J. A. ^{[1
]}

机构：

[1] ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France

[2] Lawrence Livermore Natl Lab, POB 808, Livermore, CA USA

[3] 1166 Bordeaux St, Pleasanton, CA 94566 USA

来源：

NUCLEAR FUSION | 2016年 / 56卷 / 12期

关键词：

ITER; CORSICA; hybrid operation scenario; SIMULATION; DISCHARGES; TRANSPORT; STABILITY; PLASMAS;

D O I：

10.1088/0029-5515/56/12/126002

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：

The hybrid operating mode observed in several tokamaks is characterized by further enhancement over the high plasma confinement (H-mode) associated with reduced magneto-hydro-dynamic (MHD) instabilities linked to a stationary flat safety factor (q) profile in the core region. The proposed ITER hybrid operation is currently aiming at operating for a long burn duration (>1000s) with a moderate fusion power multiplication factor, Q, of at least 5. This paper presents candidate ITER hybrid operation scenarios developed using a free-boundary transport modelling code, CORSICA, taking all relevant physics and engineering constraints into account. The ITER hybrid operation scenarios have been developed by tailoring the 15 MA baseline ITER inductive H-mode scenario. Accessible operation conditions for ITER hybrid operation and achievable range of plasma parameters have been investigated considering uncertainties on the plasma confinement and transport. ITER operation capability for avoiding the poloidal field coil current, field and force limits has been examined by applying different current ramp rates, flat-top plasma currents and densities, and pre-magnetization of the poloidal field coils. Various combinations of heating and current drive (H&CD) schemes have been applied to study several physics issues, such as the plasma current density profile tailoring, enhancement of the plasma energy confinement and fusion power generation. A parameterized edge pedestal model based on EPED1 added to the CORSICA code has been applied to hybrid operation scenarios. Finally, fully self-consistent free-boundary transport simulations have been performed to provide information on the poloidal field coil voltage demands and to study the controllability with the ITER controllers.

引用

页数：19

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