skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: NSTX Electrical Power Systems

Abstract

The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic 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 design of the NSTX electrical power system was tailored to suit the available infrastructure and electrical equipment on site. Components were analyzed to verify their suitability for use in NSTX. The total number of circuits and the location of the NSTX device drove the major changes in the Power system hardware. The NSTX has eleven (11) circuits to be fed as compared to the basic three power loops for TFTR. This required changes in cabling to insure that each cable tray system has the positive and negative leg of cables in the same tray. Also additional power cabling had to be installed to the new location. The hardware had to b e modified to address the need for eleven power loops. Power converters had to be reconnected and controlled in anti-parallel mode for the Ohmic heating and two of the Poloidal Field circuits. The circuit for the Coaxialmore » Helicity Injection (CHI) System had to be carefully developed to meet this special application. Additional Protection devices were designed and installed for the magnet coils and the CHI. The thrust was to making the changes in the most cost-effective manner without compromising technical requirements. This paper describes the changes and addition to the Electrical Power System components for the NSTX magnet systems.« less

Authors:
; ; ; ;
Publication Date:
Research Org.:
Princeton Plasma Physics Lab., NJ (US)
Sponsoring Org.:
USDOE Office of Energy Research (ER) (US)
OSTI Identifier:
15127
Report Number(s):
PPPL-3407
TRN: US0204568
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 16 Dec 1999
Country of Publication:
United States
Language:
English
Subject:
24 POWER TRANSMISSION AND DISTRIBUTION; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CABLES; ELECTRICAL EQUIPMENT; HEATING; HELICITY; MAGNET COILS; MAGNETS; MODIFICATIONS; NSTX DEVICE; PHYSICS; POWER SYSTEMS; TFTR TOKAMAK

Citation Formats

A. Ilic, E. Baker, R. Hatcher, S. Ramakrishnan, and et al. NSTX Electrical Power Systems. United States: N. p., 1999. Web. doi:10.2172/15127.
A. Ilic, E. Baker, R. Hatcher, S. Ramakrishnan, & et al. NSTX Electrical Power Systems. United States. doi:10.2172/15127.
A. Ilic, E. Baker, R. Hatcher, S. Ramakrishnan, and et al. Thu . "NSTX Electrical Power Systems". United States. doi:10.2172/15127. https://www.osti.gov/servlets/purl/15127.
@article{osti_15127,
title = {NSTX Electrical Power Systems},
author = {A. Ilic and E. Baker and R. Hatcher and S. Ramakrishnan and et al},
abstractNote = {The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic 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 design of the NSTX electrical power system was tailored to suit the available infrastructure and electrical equipment on site. Components were analyzed to verify their suitability for use in NSTX. The total number of circuits and the location of the NSTX device drove the major changes in the Power system hardware. The NSTX has eleven (11) circuits to be fed as compared to the basic three power loops for TFTR. This required changes in cabling to insure that each cable tray system has the positive and negative leg of cables in the same tray. Also additional power cabling had to be installed to the new location. The hardware had to b e modified to address the need for eleven power loops. Power converters had to be reconnected and controlled in anti-parallel mode for the Ohmic heating and two of the Poloidal Field circuits. The circuit for the Coaxial Helicity Injection (CHI) System had to be carefully developed to meet this special application. Additional Protection devices were designed and installed for the magnet coils and the CHI. The thrust was to making the changes in the most cost-effective manner without compromising technical requirements. This paper describes the changes and addition to the Electrical Power System components for the NSTX magnet systems.},
doi = {10.2172/15127},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Dec 16 00:00:00 EST 1999},
month = {Thu Dec 16 00:00:00 EST 1999}
}

Technical Report:

Save / Share: