Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction

D. A. Gates; J. R. Ferron; M. Bell; T. Gibney; R. Johnson; R. J. Marsala; D. Mastrovito; J. E. Menard; D. Mueller; B. Penaflor; S. A. Sabbagh; T. Stevenson

doi:10.1088/0029-5515/46/1/002

Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction

D. A. Gates
, J. R. Ferron
, M. Bell
, T. Gibney
, R. Johnson
, R. J. Marsala
, D. Mastrovito
, J. E. Menard
, D. Mueller
, B. Penaflor
, S. A. Sabbagh
, T. Stevenson

PPPL Advanced Projects

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

69 Scopus citations

Abstract

Plasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DIII-D was adapted for use on NSTX. The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.

Original language	English (US)
Pages (from-to)	17-23
Number of pages	7
Journal	Nuclear Fusion
Volume	46
Issue number	1
DOIs	https://doi.org/10.1088/0029-5515/46/1/002
State	Published - Jan 1 2006

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

Access to Document

10.1088/0029-5515/46/1/002

Cite this

@article{ed537da2448a4e2796b36c9e5498fdd0,

title = "Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction",

abstract = "Plasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DIII-D was adapted for use on NSTX. The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.",

author = "Gates, \{D. A.\} and Ferron, \{J. R.\} and M. Bell and T. Gibney and R. Johnson and Marsala, \{R. J.\} and D. Mastrovito and Menard, \{J. E.\} and D. Mueller and B. Penaflor and Sabbagh, \{S. A.\} and T. Stevenson",

year = "2006",

month = jan,

day = "1",

doi = "10.1088/0029-5515/46/1/002",

language = "English (US)",

volume = "46",

pages = "17--23",

journal = "Nuclear Fusion",

issn = "0029-5515",

publisher = "IOP Publishing Ltd.",

number = "1",

}

TY - JOUR

T1 - Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction

AU - Gates, D. A.

AU - Ferron, J. R.

AU - Bell, M.

AU - Gibney, T.

AU - Johnson, R.

AU - Marsala, R. J.

AU - Mastrovito, D.

AU - Menard, J. E.

AU - Mueller, D.

AU - Penaflor, B.

AU - Sabbagh, S. A.

AU - Stevenson, T.

PY - 2006/1/1

Y1 - 2006/1/1

N2 - Plasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DIII-D was adapted for use on NSTX. The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.

AB - Plasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DIII-D was adapted for use on NSTX. The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.

UR - https://www.scopus.com/pages/publications/29244442613

UR - https://www.scopus.com/pages/publications/29244442613#tab=citedBy

U2 - 10.1088/0029-5515/46/1/002

DO - 10.1088/0029-5515/46/1/002

M3 - Article

AN - SCOPUS:29244442613

SN - 0029-5515

VL - 46

SP - 17

EP - 23

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 1

ER -

Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction

Abstract

All Science Journal Classification (ASJC) codes

Access to Document

Other files and links

Fingerprint

Cite this