Hardwired control system changes for NSTX DC power feeds

S. Ramakrishnan; Xin Zhao; C. Neumeyer; J. Lawson; R. Hatcher; R. Mozulay; E. Baker; W. Que

doi:10.1109/SOFE.2013.6635282

Hardwired control system changes for NSTX DC power feeds

S. Ramakrishnan
, Xin Zhao
, C. Neumeyer
, J. Lawson
, R. Hatcher
, R. Mozulay
, E. Baker
, W. Que

PPPL Engineering

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

1 Scopus citations

Abstract

The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. The original TFTR Hardwired Control System (HCS) with electromechanical relays was used for NSTX DC Power loop control and protection during NSTX operations. As part of the NSTX Upgrade, the HCS is being changed to a PLC-based system with the same control logic. This paper gives a description of the changeover to the new PLC-based system

Original language	English (US)
Title of host publication	2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
DOIs	https://doi.org/10.1109/SOFE.2013.6635282
State	Published - 2013
Event	2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 - San Francisco, CA, United States Duration: Jun 10 2013 → Jun 14 2013

Publication series

Name	2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013

Other

Other	2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
Country/Territory	United States
City	San Francisco, CA
Period	6/10/13 → 6/14/13

All Science Journal Classification (ASJC) codes

Software

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10.1109/SOFE.2013.6635282

Cite this

@inproceedings{eb7f06b82b07429d92bb4653a284fbb2,

title = "Hardwired control system changes for NSTX DC power feeds",

abstract = "The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. The original TFTR Hardwired Control System (HCS) with electromechanical relays was used for NSTX DC Power loop control and protection during NSTX operations. As part of the NSTX Upgrade, the HCS is being changed to a PLC-based system with the same control logic. This paper gives a description of the changeover to the new PLC-based system",

author = "S. Ramakrishnan and Xin Zhao and C. Neumeyer and J. Lawson and R. Hatcher and R. Mozulay and E. Baker and W. Que",

year = "2013",

doi = "10.1109/SOFE.2013.6635282",

language = "English (US)",

isbn = "9781479901715",

series = "2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013",

booktitle = "2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013",

note = "2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 ; Conference date: 10-06-2013 Through 14-06-2013",

}

Ramakrishnan, S, Zhao, X, Neumeyer, C, Lawson, J, Hatcher, R, Mozulay, R, Baker, E & Que, W 2013, Hardwired control system changes for NSTX DC power feeds. in 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013., 6635282, 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013, 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013, San Francisco, CA, United States, 6/10/13. https://doi.org/10.1109/SOFE.2013.6635282

TY - GEN

T1 - Hardwired control system changes for NSTX DC power feeds

AU - Ramakrishnan, S.

AU - Zhao, Xin

AU - Neumeyer, C.

AU - Lawson, J.

AU - Hatcher, R.

AU - Mozulay, R.

AU - Baker, E.

AU - Que, W.

PY - 2013

Y1 - 2013

N2 - The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. The original TFTR Hardwired Control System (HCS) with electromechanical relays was used for NSTX DC Power loop control and protection during NSTX operations. As part of the NSTX Upgrade, the HCS is being changed to a PLC-based system with the same control logic. This paper gives a description of the changeover to the new PLC-based system

AB - The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. The original TFTR Hardwired Control System (HCS) with electromechanical relays was used for NSTX DC Power loop control and protection during NSTX operations. As part of the NSTX Upgrade, the HCS is being changed to a PLC-based system with the same control logic. This paper gives a description of the changeover to the new PLC-based system

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UR - https://www.scopus.com/pages/publications/84890460893#tab=citedBy

U2 - 10.1109/SOFE.2013.6635282

DO - 10.1109/SOFE.2013.6635282

M3 - Conference contribution

AN - SCOPUS:84890460893

SN - 9781479901715

T3 - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013

BT - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013

T2 - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013

Y2 - 10 June 2013 through 14 June 2013

ER -

Hardwired control system changes for NSTX DC power feeds

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