Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak)
Abstract
The free-boundary equilibrium code VEQ provides equilibrium data that are used by the Tokamak Simulation Code (TSC) in design and analysis of the poloidal field (PF) system for the Compact Ignition Tokamak (CIT). VEQ serves as an important design tool for locating the PF coils and defining coil current trajectories and control systems for TSC. In this report, VEQ and its role in the TSC analysis of the CIT PF system are described. Equilibrium and coil current calculations are discussed, an overview of the CIT PF system is presented, a set of reference equilibria for modeling a complete discharge in CIT is described, and the concept of a plasma shape control matrix is introduced. 9 refs., 8 figs., 7 tabs.
- Authors:
-
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- Princeton Univ., NJ (USA). Plasma Physics Lab.
- Publication Date:
- Research Org.:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- Sponsoring Org.:
- DOE/ER
- OSTI Identifier:
- 7222670
- Report Number(s):
- ORNL/FEDC-89/4
ON: DE90008086; TRN: 90-008286
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; MHD EQUILIBRIUM; PLASMA SIMULATION; POLOIDAL FIELD DIVERTORS; DESIGN; COMPACT IGNITION TOKAMAK; COMPUTER CALCULATIONS; COMPUTERIZED CONTROL SYSTEMS; CURRENT DENSITY; LIMITERS; PLASMA DISRUPTION; V CODES; CLOSED PLASMA DEVICES; COMPUTER CODES; CONTROL SYSTEMS; DIVERTORS; EQUILIBRIUM; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; 700209* - Fusion Power Plant Technology- Component Development & Materials Testing; 700103 - Fusion Energy- Plasma Research- Kinetics
Citation Formats
Strickler, D J, Peng, Y-K M, Pomphrey, N, and Jardin, S C. Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak). United States: N. p., 1990.
Web. doi:10.2172/7222670.
Strickler, D J, Peng, Y-K M, Pomphrey, N, & Jardin, S C. Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak). United States. https://doi.org/10.2172/7222670
Strickler, D J, Peng, Y-K M, Pomphrey, N, and Jardin, S C. 1990.
"Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak)". United States. https://doi.org/10.2172/7222670. https://www.osti.gov/servlets/purl/7222670.
@article{osti_7222670,
title = {Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak)},
author = {Strickler, D J and Peng, Y-K M and Pomphrey, N and Jardin, S C},
abstractNote = {The free-boundary equilibrium code VEQ provides equilibrium data that are used by the Tokamak Simulation Code (TSC) in design and analysis of the poloidal field (PF) system for the Compact Ignition Tokamak (CIT). VEQ serves as an important design tool for locating the PF coils and defining coil current trajectories and control systems for TSC. In this report, VEQ and its role in the TSC analysis of the CIT PF system are described. Equilibrium and coil current calculations are discussed, an overview of the CIT PF system is presented, a set of reference equilibria for modeling a complete discharge in CIT is described, and the concept of a plasma shape control matrix is introduced. 9 refs., 8 figs., 7 tabs.},
doi = {10.2172/7222670},
url = {https://www.osti.gov/biblio/7222670},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}
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