Plasma flux expansion control on the DIII-D tokamak

被引：8

作者：

Anand, H. ^{[1
]}

Humphreys, D. ^{[1
]}

Eldon, D. ^{[1
]}

Leonard, A. ^{[1
]}

Hyatt, A. ^{[1
]}

Sammuli, B. ^{[1
]}

Welander, A. ^{[1
]}

机构：

[1] Gen Atom, DIII D Natl Fus Facil, POB 85608, San Diego, CA 92186 USA

来源：

PLASMA PHYSICS AND CONTROLLED FUSION | 2021年 / 63卷 / 01期

关键词：

real-time control; magnetic control; scrape-off layer; flux expansion; magnetic equilibrium reconstruction; MAST-UPGRADE; ITER;

D O I：

10.1088/1361-6587/abc457

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：

A new controller has been developed with help of the flexible divertor poloidal-field coil set of the DIII-D tokamak, to aid in the precise control of the flux expansion in the scrape-off layer. The single-input multiple-output architecture ensures flexibility through a complementary set of orthogonal actuator direction to guarantee minimum effect on existing controlled variables, e.g. radial and vertical position control of the X-point. A non-linear free-boundary simulation code (GSevolve) is used for simulating the closed-loop response and for verifying the implementation of the control algorithm on the DIII-D plasma control system. First results of the experimental commissioning of the new controller during 2020 DIII-D campaign are also presented.

引用

页数：7

共 17 条

[1]

Albanese R., 2016, 2016 IEEE Conference on Control Applications (CCA), P611, DOI 10.1109/CCA.2016.7587897

[2] Increased heat dissipation with the X-divertor geometry facilitating detachment onset at lower density in DIII-D [J].

Covele, B. ;

Kotschenreuther, M. ;

Mahajan, S. ;

Valanju, P. ;

Leonard, A. ;

Watkins, J. ;

Makowski, M. ;

Fenstermacher, M. ;

Si, H. .

NUCLEAR FUSION, 2017, 57 (08)

[3] Implementing a finite-state off-normal and fault response system for disruption avoidance in tokamaks [J].

Eidietis, N. W. ;

Choi, W. ;

Hahn, S. H. ;

Humphreys, D. A. ;

Sammuli, B. S. ;

Walker, M. L. .

NUCLEAR FUSION, 2018, 58 (05)

[4] Real time equilibrium reconstruction for tokamak discharge control [J].

Ferron, JR ;

Walker, ML ;

Lag, LL ;

St John, HE ;

Humphreys, DA ;

Leuer, JA .

NUCLEAR FUSION, 1998, 38 (07) :1055-1066

[5] MAST-upgrade divertor facility and assessing performance of long-legged divertors [J].

Fishpool, G. ;

Canik, J. ;

Cunningham, G. ;

Harrison, J. ;

Katramados, I. ;

Kirk, A. ;

Kovari, M. ;

Meyer, H. ;

Scannell, R. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S356-S359

[6] DIII-D Integrated plasma control solutions for ITER and next-generation tokamaks [J].

Humphreys, D. A. ;

Ferron, J. R. ;

Hyatt, A. W. ;

La Haye, R. J. ;

Leuer, J. A. ;

Penaflor, B. G. ;

Walker, M. L. ;

Welander, A. S. ;

In, Y. .

FUSION ENGINEERING AND DESIGN, 2008, 83 (2-3) :193-197

[7] Development of ITER-relevant plasma control solutions at DIII-D [J].

Humphreys, D. A. ;

Ferron, J. R. ;

Bakhtiari, M. ;

Blair, J. A. ;

In, Y. ;

Jackson, G. L. ;

Jhang, H. ;

Johnson, R. D. ;

Kim, J. S. ;

LaHaye, R. J. ;

Leuer, J. A. ;

Penaflor, B. G. ;

Schuster, E. ;

Walker, M. L. ;

Wang, H. ;

Welander, A. S. ;

Whyte, D. G. .

NUCLEAR FUSION, 2007, 47 (08) :943-951

[8] Magnetic geometry and physics of advanced divertors: The X-divertor and the snowflake [J].

Kotschenreuther, Mike ;

Valanju, Prashant ;

Covele, Brent ;

Mahajan, Swadesh .

PHYSICS OF PLASMAS, 2013, 20 (10)

[9] A design retrospective of the DIII-D tokamak [J].

Luxon, JL .

NUCLEAR FUSION, 2002, 42 (05) :614-633

[10] MAST Upgrade - Construction Status [J].

Milnes, Joe ;

Ben Ayed, Nizar ;

Dhalla, Fahim ;

Fishpool, Geoff ;

Hill, John ;

Katramados, Ioannis ;

Martin, Richard ;

Naylor, Graham ;

O'Gorman, Tom ;

Scannell, Rory .

FUSION ENGINEERING AND DESIGN, 2015, 96-97 :42-47

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