Equilibrium shape control in CIT (Compact Ignition Tokamak) PF (poloidal field) design

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5393719

Strickler, D J; Pomphrey, N; Jardin, S C ^[1]

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1. Oak Ridge National Lab., TN (USA)

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 paper, VEQ and its role in the TSC analysis of the CIT PF system are described. 7 refs., 5 figs., 6 tabs.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5393719
• Report Number(s): CONF-891007-78; ON: DE90002487
• Resource Relation: Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
POLOIDAL FIELD DIVERTORS
COMPUTER-AIDED DESIGN
COMPACT IGNITION TOKAMAK
COMPUTERIZED SIMULATION
CONTROL SYSTEMS
CURRENT DENSITY
MHD EQUILIBRIUM
CLOSED PLASMA DEVICES
DIVERTORS
EQUILIBRIUM
SIMULATION
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields