Simulation of DIII-D Flat q Discharges

Technical Report · Fri Jun 25 04:00:00 EDT 2004

DOI:https://doi.org/10.2172/828256· OSTI ID:828256

Kessel, C E ^[1]; Garofalo, A; Terpstra, T

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1. Princeton Plasma Physics Laboratory

The Advanced Tokamak plasma configuration has significant potential for the economical production of fusion power. Research on various tokamak experiments are pursuing these plasmas to establish high {beta}, high bootstrap current fraction, 100% noninductive current, and good energy confinement, in a quasi-stationary state. One candidate is the flat q discharge produced in DIII-D, where the safety factor varies from 2.0 on axis, to slightly below 2.0 at the minimum, and then rises to about 3.5 at the 95% surface. This plasma is prototypical of those studied for power plants in the ARIES tokamak studies. The plasma is produced by ramping up the plasma current and ramping down the toroidal field throughout the discharge. The plasma current reaches 1.65 MA, and the toroidal field goes from 2.25 to 1.6 T. The q{sub min} remains high and at large radius, {rho} {approx} 0.6. The plasma establishes an internal transport barrier in the ion channel, and transitions to H-mode. The free-boundary Tokamak Simulation Code (TSC) is being used to model the discharge and project the impact of changes in the plasma current, toroidal field, and injected power programming.

• Research Organization: Princeton Plasma Physics Lab., Princeton, NJ (US)
• Sponsoring Organization: USDOE Office of Science (SC) (US)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 828256
• Report Number(s): PPPL-3972
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BOOTSTRAP CURRENT
CONFIGURATION
CONFINEMENT
DOUBLET-3 DEVICE
ELECTRIC CURRENTS
MAGNETOHYDRODYNAMICS (MHD)
PLASMA
POWER PLANTS
PRODUCTION
PROGRAMMING
SAFETY
SIMULATION
TOKAMAKS
TRANSPORT
TRANSPORT EQUATIONS