Current Status of EAST Plasma Control and Data Acquisition

被引：7

作者：

Xiao, B. J. ^{[1
]}

Ji, Z. S. ^{[1
]}

Shen, B. ^{[1
]}

Li, G. M. ^{[1
]}

Wang, H. Z. ^{[1
]}

Wang, F. ^{[1
]}

Yuan, Q. P. ^{[1
]}

Yang, F. ^{[1
]}

Sun, X. Y. ^{[1
]}

Luo, J. R. ^{[1
]}

Wang, Y. ^{[1
]}

Wu, Y. C. ^{[1
]}

Zhang, R. R. ^{[1
]}

Luo, Z. P. ^{[1
]}

Dang, N. ^{[1
]}

Li, S. ^{[1
]}

Zhou, Z. Y. ^{[1
]}

Wang, P. ^{[1
]}

Humphreys, D. A. ^{[2
]}

Walker, M. L. ^{[2
]}

Hyatt, A. ^{[2
]}

Leuer, J. A. ^{[2
]}

Welander, A. ^{[2
]}

Johnson, R. D. ^{[2
]}

Penaflor, B. G. ^{[2
]}

Piglowski, D. A. ^{[2
]}

Mueller, D. ^{[3
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China

[2] Gen Atom Co, DIII Natl Fus Facil D, San Diego, CA 92186 USA

[3] Princeton Plasma Phys Lab, Princeton, NJ 08540 USA

来源：

IEEE TRANSACTIONS ON NUCLEAR SCIENCE | 2010年 / 57卷 / 02期

关键词：

EAST tokomak; data acquisition; plasma control; CONTROL-SYSTEM; RECONSTRUCTION; TOKAMAKS;

D O I：

10.1109/TNS.2010.2042067

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

This paper briefly outlines the current status of CODAC system of the EAST tokamak. Integrated central system has been working for synchronizing all the subsystems and responsible for the integral safety protection by interlock. Data acquisition system has been established for the discharge with duration up to 100 seconds. Various data visualization tools such as EASTVIEWER to view the flux surfaces, RTSCOPE to view plasma boundary and CCD image in real-time, WEBSCOPE to view the diagnostic data via a web browser and EASTVOD to view and search plasma discharge image at different time, haven developed for EAST operation. Plasma control system is inherited from DIII-D, and has been matured to a stage to feedback control the EAST plasma shape, density and current in real time.

引用

页码：510 / 514

页数：5

共 19 条

[1]

Dang D., 2009, 16 IEEE NPSS REAL TI

[2] 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

[3] 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

[4] RECONSTRUCTION OF CURRENT PROFILE PARAMETERS AND PLASMA SHAPES IN TOKAMAKS [J].

LAO, LL ;

STJOHN, H ;

STAMBAUGH, RD ;

KELLMAN, AG ;

PFEIFFER, W .

NUCLEAR FUSION, 1985, 25 (11) :1611-1622

[5]

LI GM, 2009, 16 IEEE NPSS REAL TI

[6]

Luo Z. P., 2009, 16 IEEE NPSS REAL TI

[7] Worldwide collaborative efforts in plasma control software development [J].

Penaflor, B. G. ;

Ferron, J. R. ;

Walker, M. L. ;

Humphreys, D. A. ;

Leuer, J. A. ;

Piglowski, D. A. ;

Johnson, R. D. ;

Xiao, B. J. ;

Hahn, S. H. ;

Gates, D. A. .

FUSION ENGINEERING AND DESIGN, 2008, 83 (2-3) :176-180

[8]

Peng Q, 1999, P 11 IEEE NPSS REAL

[9]

SUN XY, 2009, 16 IEEE NPSS REAL TI

[10] Next-generation plasma control in the DIII-D tokamak [J].

Walker, ML ;

Ferron, JR ;

Humphreys, DA ;

Johnson, RD ;

Leuer, JA ;

Penaflor, BG ;

Piglowski, DA ;

Ariola, M ;

Pironti, A ;

Schuster, E .

FUSION ENGINEERING AND DESIGN, 2003, 66-68 :749-753

← 1 2 →