The high-βN hybrid scenario for ITER and FNSF steady-state missions

被引：37

作者：

Turco, F. ^{[1
]}

Petty, C. C. ^{[2
]}

Luce, T. C. ^{[2
]}

Carlstrom, T. N. ^{[2
]}

Van Zeeland, M. A. ^{[2
]}

Heidbrink, W. ^{[3
]}

Carpanese, F. ^{[4
]}

Solomon, W. ^{[5
]}

Holcomb, C. T. ^{[6
]}

Ferron, J. R. ^{[2
]}

机构：

[1] Columbia Univ, New York, NY 10027 USA

[2] Gen Atom Co, San Diego, CA 92186 USA

[3] Univ Calif Irvine, Irvine, CA 92697 USA

[4] Politecn Milan, Dipartimento Energia, I-20133 Milan, Italy

[5] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[6] Lawrence Livermore Natl Lab, Livermore, CA 94550 USA

来源：

PHYSICS OF PLASMAS | 2015年 / 22卷 / 05期

关键词：

PHYSICS BASIS; DISCHARGES; BETA;

D O I：

10.1063/1.4921161

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：

New experiments on DIII-D have demonstrated the steady-state potential of the hybrid scenario, with 1 MA of plasma current driven fully non-inductively and beta(N) up to 3.7 sustained for similar to 3 s (similar to 1.5 current diffusion time, tau(R), in DIII-D), providing the basis for an attractive option for steady-state operation in ITER and FNSF. Excellent confinement is achieved (H-98y2 similar to 1.6) without performance limiting tearing modes. The hybrid regime overcomes the need for off-axis current drive efficiency, taking advantage of poloidal magnetic flux pumping that is believed to be the result of a saturated 3/2 tearing mode. This allows for efficient current drive close to the axis, without deleterious sawtooth instabilities. In these experiments, the edge surface loop voltage is driven down to zero for > 1 tau(R) when the poloidal beta is increased above 1.9 at a plasma current of 1.0 MA and the ECH power is increased to 3.2MW. Stationary operation of hybrid plasmas with all on-axis current drive is sustained at pressures slightly above the ideal no-wall limit, while the calculated ideal with-wall MHD limit is beta(N) similar to 4-4.5. Off-axis Neutral Beam Injection (NBI) power has been used to broaden the pressure and current profiles in this scenario, seeking to take advantage of higher predicted kink stability limits and lower values of the tearing stability index Delta', as calculated by the DCON and PEST3 codes. Results based on measured profiles predict ideal limits at beta(N)> 4.5, 10% higher than the cases with on-axis NBI. A 0-D model, based on the present confinement, beta(N) and shape values of the DIII-D hybrid scenario, shows that these plasmas are consistent with the ITER 9 MA, Q = 5 mission and the FNSF 6.7 MA scenario with Q = 3.5. With collisionality and edge safety factor values comparable to those envisioned for ITER and FNSF, the high-beta(N) hybrid represents an attractive high performance option for the steady-state missions of these devices. (C) 2015 AIP Publishing LLC.

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