Equilibrium calculations for plasma control in CIT (Compact Ignition Tokamak)

Technical Report · Mon Jan 01 00:00:00 EST 1990

DOI:https://doi.org/10.2172/7222670· OSTI ID:7222670

Strickler, D J; Peng, Y-K M ^[1]; Pomphrey, N; Jardin, S C ^[2]

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1. Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
2. Princeton Univ., NJ (USA). Plasma Physics Lab.

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.

• Research Organization: Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7222670
• Report Number(s): ORNL/FEDC-89/4; ON: DE90008086; TRN: 90-008286
• Country of Publication: United States
• Language: English

Related Subjects

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
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