Standard

Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER. / Belyakov, V.; Kavin, A.; Kharitonov, V.; Misenov, B.; Mitrishkin, Y.; Ovsyannikov, A.; Ovsyannikov, D.; Rumyantsev, E.; Veremei, E.; Zhabko, A.

In: Fusion Engineering and Design, Vol. 45, No. 1, 1999, p. 55-64.

Research output: Contribution to journal › Article › peer-review

Harvard

Belyakov, V, Kavin, A, Kharitonov, V, Misenov, B, Mitrishkin, Y, Ovsyannikov, A, Ovsyannikov, D, Rumyantsev, E, Veremei, E & Zhabko, A 1999, 'Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER', Fusion Engineering and Design, vol. 45, no. 1, pp. 55-64.

APA

Belyakov, V., Kavin, A., Kharitonov, V., Misenov, B., Mitrishkin, Y., Ovsyannikov, A., Ovsyannikov, D., Rumyantsev, E., Veremei, E., & Zhabko, A. (1999). Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER. Fusion Engineering and Design, 45(1), 55-64.

Vancouver

Belyakov V, Kavin A, Kharitonov V, Misenov B, Mitrishkin Y, Ovsyannikov A et al. Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER. Fusion Engineering and Design. 1999;45(1):55-64.

Author

Belyakov, V. ; Kavin, A. ; Kharitonov, V. ; Misenov, B. ; Mitrishkin, Y. ; Ovsyannikov, A. ; Ovsyannikov, D. ; Rumyantsev, E. ; Veremei, E. ; Zhabko, A. / Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER. In: Fusion Engineering and Design. 1999 ; Vol. 45, No. 1. pp. 55-64.

BibTeX

@article{65bcce34b7dc4474818de06215802c3f,
title = "Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER",
abstract = "This paper is focused on the linear quadratic Gaussian (LQG) controller synthesis methodology for the ITER plasma current, position and shape control system as well as power derivative management system. It has been shown that some poloidal field (PF) coils have less influence on reference plasma-wall gaps control during plasma disturbances and hence they have been used to reduce total control power derivative by means of the additional non-linear feedback. The design has been done on the basis of linear models. Simulation was provided for non-linear model and results are presented and discussed.",
keywords = "ITER, Linear quadratic Gaussian controller, Plasma current, Position and shape control, Tokamak",
author = "V. Belyakov and A. Kavin and V. Kharitonov and B. Misenov and Y. Mitrishkin and A. Ovsyannikov and D. Ovsyannikov and E. Rumyantsev and E. Veremei and A. Zhabko",
year = "1999",
language = "English",
volume = "45",
pages = "55--64",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier",
number = "1",

}

RIS

TY - JOUR

T1 - Linear quadratic Gaussian controller design for plasma current, position and shape control system in ITER

AU - Belyakov, V.

AU - Kavin, A.

AU - Kharitonov, V.

AU - Misenov, B.

AU - Mitrishkin, Y.

AU - Ovsyannikov, A.

AU - Ovsyannikov, D.

AU - Rumyantsev, E.

AU - Veremei, E.

AU - Zhabko, A.

PY - 1999

Y1 - 1999

N2 - This paper is focused on the linear quadratic Gaussian (LQG) controller synthesis methodology for the ITER plasma current, position and shape control system as well as power derivative management system. It has been shown that some poloidal field (PF) coils have less influence on reference plasma-wall gaps control during plasma disturbances and hence they have been used to reduce total control power derivative by means of the additional non-linear feedback. The design has been done on the basis of linear models. Simulation was provided for non-linear model and results are presented and discussed.

AB - This paper is focused on the linear quadratic Gaussian (LQG) controller synthesis methodology for the ITER plasma current, position and shape control system as well as power derivative management system. It has been shown that some poloidal field (PF) coils have less influence on reference plasma-wall gaps control during plasma disturbances and hence they have been used to reduce total control power derivative by means of the additional non-linear feedback. The design has been done on the basis of linear models. Simulation was provided for non-linear model and results are presented and discussed.

KW - ITER

KW - Linear quadratic Gaussian controller

KW - Plasma current

KW - Position and shape control

KW - Tokamak

UR - http://www.scopus.com/inward/record.url?scp=0033101255&partnerID=8YFLogxK

M3 - Article

AN - SCOPUS:0033101255

VL - 45

SP - 55

EP - 64

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 1

ER -

ID: 9423957