Feasibility Study of a Compact Ignition Tokamak Based upon GyroBohm Scaling Physics

The design of a reduced size (R = 4.45 m, B T = 5.04 T) ignition tokamak (Q = ∞) with superconducting coils using a standard ELMing H-mode plasma appears to be feasible. This effective size (B T 2/3 R 5/6 ) is smaller than current proposals for Q = 10 burning (D-T) plasma experiments. The good confi...

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Bibliographic Details
Published in:Fusion science and technology 2003-01, Vol.43 (1), p.1-17
Main Authors: Petty, Clinton Craig, DeBoo, James Craig, Haye, Robert John La, Luce, Timothy Charles, Politzer, Peter A., Wong, Clement Po-Ching
Format: Article
Language:English
Subjects:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPACT IGNITION TOKAMAK
D-T OPERATION
DESIGN
EDGE LOCALIZED MODES
ELECTRIC CURRENTS
FEASIBILITY STUDIES
H-MODE PLASMA CONFINEMENT
HIGH-BETA PLASMA
SOLENOIDS
SUPERCONDUCTING COILS
THERMONUCLEAR IGNITION
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Summary:The design of a reduced size (R = 4.45 m, B T = 5.04 T) ignition tokamak (Q = ∞) with superconducting coils using a standard ELMing H-mode plasma appears to be feasible. This effective size (B T 2/3 R 5/6 ) is smaller than current proposals for Q = 10 burning (D-T) plasma experiments. The good confinement required for ignition with this small effective size is obtained by operating along a gyroBohm scaling path starting from the existing tokamak database at high beta (β = 4.1%) so that the loss power from core transport exceeds the H-mode threshold power. Using a design that can achieve a high normalized current (I p /aB T = 1.63) also helps to decrease the size of the machine. The design of this relatively compact ignition tokamak satisfies reasonable engineering constraints on the superconducting toroidal field coils and central solenoid, and allows for a sufficiently long burn time for the plasma current to relax to its final state.
ISSN:1536-1055
1943-7641
DOI:10.13182/FST03-A245