Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade

R. D. Woolley; P. H. Titus; C. L. Neumeyer; R. E. Hatcher

doi:10.1109/SOFE.2011.6052262

Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade

R. D. Woolley, P. H. Titus, C. L. Neumeyer, R. E. Hatcher

PPPL Engineering

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

8 Scopus citations

Abstract

A significant upgrade is planned for the National Spherical Torus eXperiment (NSTX) in which plasma current and confining magnetic field intensities will nearly double while plasma duration will more than double. Changes will include replacing the existing centerstack with a new one containing a thicker TF inner Leg, a new OH solenoid coil, and an expansion to six of the complement of PF1 coils controlling plasma divertor shape. Other coils will remain in service with hardware modifications as needed for their approximately three-fold increases in magnetic forces.

Original language	English (US)
Title of host publication	2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011
DOIs	https://doi.org/10.1109/SOFE.2011.6052262
State	Published - 2011
Event	2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011 - Chicago, IL, United States Duration: Jun 26 2011 → Jun 30 2011

Publication series

Name	Proceedings - Symposium on Fusion Engineering

Other

Other	2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011
Country/Territory	United States
City	Chicago, IL
Period	6/26/11 → 6/30/11

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Keywords

coils
equipment safety
protection

Access to Document

10.1109/SOFE.2011.6052262

Cite this

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title = "Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade",

abstract = "A significant upgrade is planned for the National Spherical Torus eXperiment (NSTX) in which plasma current and confining magnetic field intensities will nearly double while plasma duration will more than double. Changes will include replacing the existing centerstack with a new one containing a thicker TF inner Leg, a new OH solenoid coil, and an expansion to six of the complement of PF1 coils controlling plasma divertor shape. Other coils will remain in service with hardware modifications as needed for their approximately three-fold increases in magnetic forces.",

keywords = "coils, equipment safety, protection",

author = "Woolley, \{R. D.\} and Titus, \{P. H.\} and Neumeyer, \{C. L.\} and Hatcher, \{R. E.\}",

year = "2011",

doi = "10.1109/SOFE.2011.6052262",

language = "English (US)",

isbn = "9781457706691",

series = "Proceedings - Symposium on Fusion Engineering",

booktitle = "2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011",

note = "2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011 ; Conference date: 26-06-2011 Through 30-06-2011",

}

Woolley, RD, Titus, PH, Neumeyer, CL & Hatcher, RE 2011, Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade. in 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011., 6052262, Proceedings - Symposium on Fusion Engineering, 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011, Chicago, IL, United States, 6/26/11. https://doi.org/10.1109/SOFE.2011.6052262

TY - GEN

T1 - Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade

AU - Woolley, R. D.

AU - Titus, P. H.

AU - Neumeyer, C. L.

AU - Hatcher, R. E.

PY - 2011

Y1 - 2011

N2 - A significant upgrade is planned for the National Spherical Torus eXperiment (NSTX) in which plasma current and confining magnetic field intensities will nearly double while plasma duration will more than double. Changes will include replacing the existing centerstack with a new one containing a thicker TF inner Leg, a new OH solenoid coil, and an expansion to six of the complement of PF1 coils controlling plasma divertor shape. Other coils will remain in service with hardware modifications as needed for their approximately three-fold increases in magnetic forces.

AB - A significant upgrade is planned for the National Spherical Torus eXperiment (NSTX) in which plasma current and confining magnetic field intensities will nearly double while plasma duration will more than double. Changes will include replacing the existing centerstack with a new one containing a thicker TF inner Leg, a new OH solenoid coil, and an expansion to six of the complement of PF1 coils controlling plasma divertor shape. Other coils will remain in service with hardware modifications as needed for their approximately three-fold increases in magnetic forces.

KW - coils

KW - equipment safety

KW - protection

UR - https://www.scopus.com/pages/publications/80955124655

UR - https://www.scopus.com/inward/citedby.url?scp=80955124655&partnerID=8YFLogxK

U2 - 10.1109/SOFE.2011.6052262

DO - 10.1109/SOFE.2011.6052262

M3 - Conference contribution

AN - SCOPUS:80955124655

SN - 9781457706691

T3 - Proceedings - Symposium on Fusion Engineering

BT - 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011

T2 - 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011

Y2 - 26 June 2011 through 30 June 2011

ER -

Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade

Abstract

Publication series

Other

All Science Journal Classification (ASJC) codes

Keywords

Access to Document

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