Plasma boundary shape control and realt-ime equilibrium reconstruction on NSTX-U

被引：24

作者：

Boyer, M. D. ^{[1
]}

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

Mueller, D. ^{[1
]}

Eidietis, N. ^{[2
]}

Erickson, K. ^{[1
]}

Ferron, J. ^{[2
]}

Gates, D. A. ^{[1
]}

Gerhardt, S. ^{[1
]}

Johnson, R. ^{[2
]}

Kolemen, E. ^{[3
]}

Menard, J. ^{[1
]}

Myers, C. E. ^{[1
]}

Sabbagh, S. A. ^{[4
]}

Scotti, F. ^{[5
]}

Vail, P. ^{[3
]}

机构：

[1] Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA

[2] Gen Atom, San Diego, CA USA

[3] Princeton Univ, Dept Mech & Aerosp Engn, Princeton, NJ 08544 USA

[4] Columbia Univ, Dept Appl Phys & Appl Math, New York, NY USA

[5] Lawrence Livermore Natl Lab, Livermore, CA USA

来源：

NUCLEAR FUSION | 2018年 / 58卷 / 03期

关键词：

spherical torus; plasma boundary control; plasma boundary reconstruction; MIMO feedback control; SPHERICAL TORUS EXPERIMENT; LOW-ASPECT-RATIO; TOKAMAK; MAST; CONFINEMENT; PHYSICS; SYSTEM;

D O I：

10.1088/1741-4326/aaa4d0

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 upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a larger center-stack, enabling higher toroidal field and longer pulse duration, and the addition of three new tangentially aimed neutral beam sources, which increase available heating and current drive, and allow for flexibility in shaping power, torque, current, and particle deposition profiles. To best use these new capabilities and meet the high-performance operational goals of NSTX-U, major upgrades to the NSTX-U control system (NCS) hardware and software have been made. Several control algorithms, including those used for real-time equilibrium reconstruction and shape control, have been upgraded to improve and extend plasma control capabilities. As part of the commissioning phase of first plasma operations, the shape control system was tuned to control the boundary in both inner-wall limited and diverted discharges. It has been used to accurately track the requested evolution of the boundary (including the size of the inner gap between the plasma and central solenoid, which is a challenge for the ST configuration), X-point locations, and strike point locations, enabling repeatable discharge evolutions for scenario development and diagnostic commissioning.

引用

页数：16

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