Plasma shape control calculations for BPX divertor design

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:5241809

Strickler, D J; Neilson, G H ^[1]; Jardin, S C; Pomphrey, N ^[2]

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

The Burning Plasma Experiment (BPX) divertor is to be capable of withstanding heat loads corresponding to ignited operation and 500 MW of fusion power for a current rise time and flattop lasting several seconds. The poloidal field (PF), diagnostic, and feedback equilibrium control systems must provide precise X-point position control in order to sweep the separatrices across the divertor target surface and optimally distribute the heat loads. A control matrix MHD equilibrium code, BEQ, and the Tokamak Simulation Code (TSC) are used to compute preprogrammed double-null (DN) divertor sweep trajectories that maximize sweep distance while simultaneously satisfying a set of strict constraints: minimum lengths of the field lines between the X-point and strike points, minimum spacing between the inboard plasma edge and the limiter, maximum spacing between the outboard plasma edge and the ICRF antennas, minimum safety factor, and linked poloidal flux. A sequence of DN diverted equilibria and a consistent TSC fiducial discharge simulation are used in evaluating the performance of the BPX divertor shape and possible modifications. 5 refs., 10 figs.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5241809
• Report Number(s): CONF-910968-13; ON: DE92000731; TRN: 91-029122
• Resource Relation: Conference: 14. IEEE symposium on fusion engineering, San Diego, CA (United States), 30 Sep - 3 Oct 1991
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPACT IGNITION TOKAMAK
DIVERTORS
CONTROL
COMPUTERIZED CONTROL SYSTEMS
COMPUTERIZED SIMULATION
DESIGN
MAGNETIC FIELDS
MHD EQUILIBRIUM
SHAPE
T CODES
CLOSED PLASMA DEVICES
COMPUTER CODES
CONTROL SYSTEMS
EQUILIBRIUM
SIMULATION
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields