Dependence of CIT (Compact Ignition Tokamak) PF (poloidal field) coil currents on profile and shape parameters using the Control Matrix

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6358347

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

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

The plasma shaping flexibility of the Compact Ignition Tokamak (CIT) poloidal field (PF) coil set is demonstrated through MHD equilibrium calculations of optimal PF coil current distributions and their variation with poloidal beta, internal inductance, plasma 95% elongation, and 95% triangularity. Calculations of the magnetic stored energy are used to compare solutions associated with various plasma parameters. The Control Matrix (CM) equilibrium code, together with the nonlinear equation and numerical optimization software packages HYBRD, and VMCON, respectively, are used to find equilibrium coil current distributions for fixed divertor geometry, volt-seconds, and plasma profiles in order to isolate the dependence on individual parameters. A reference equilibrium and coil current distribution are chosen, and correction currents dI are determined using the CM equilibrium method to obtain other specified plasma shapes. The reference equilibrium is the {kappa} = 2 divertor at beginning of flattop (BOFT) with a minimum stored energy solution for the coil current distribution. The pressure profile function is fixed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6358347
• Report Number(s): CONF-901007-25; ON: DE91002650; TRN: 90-035702
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPACT IGNITION TOKAMAK
CURRENT DENSITY
COMPUTER ARCHITECTURE
MHD EQUILIBRIUM
OPTIMIZATION
POLOIDAL FIELD DIVERTORS
CLOSED PLASMA DEVICES
DIVERTORS
EQUILIBRIUM
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700103* - Fusion Energy- Plasma Research- Kinetics