CIT physics and engineering basis

Conference · Fri Jan 01 04:00:00 EST 1988

OSTI ID:6999831

Parker, R; Montgomery, D B; Myer, R; Pillsbury, R; Porkolab, M; Sigmar, D; Thome, R ^[1]; Bateman, G; Colestock, P; Furth, H; Goldston, R; Ignat, D; Jardin, S; Johnson, J; Kaye, S; Manickam, J; Phillips, C K; Pomphrey, N; Post, D E; Rutherford, P ; Schmidt, J; Sheffield, G; Stotler, D ^[2]; Houlberg, W; Say,

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1. Massachusetts Inst. of Tech., Cambridge, MA (USA)
2. Princeton Univ., NJ (USA). Plasma Physics Lab.

The CIT is a high-field, compact tokamak design whose objective is the study of physics issues associated with burning plasmas. The toroidal and poloidal field coils employ a copper-steel laminate, manufactured by explosive-bonding techniques, to support the forces generated by the design fields: 10 T toroidal field at the plasma center, and 21 T in the OH solenoid. A combination of internal and external PF coils provide control of the equilibrium and the ability to sweep the magnetic separatrix across the divertor plates during a pulse. At temperatures and {beta}{sub {alpha}} levels characteristic of ITER designs, the fusion power in CIT approaches 800 MW and can be the limiting factor in the pulse length. Ignition requires that the confinement time exceed present L-mode scalings by about a factor-of-two, which is anticipated to occur as a result of the operational flexibility incorporated into the design. Conventional operating limits given by {r angle}{beta}{l angle} < 3I/aB, {bar n}{sub 20} < 2B/Rq{sub e} and q{sub {Psi}} {le} 3.2 have been chosen and, in the case of MHD limits, have been justified by ideal stability analysis. The power required for CIT ignition ranges from 10 MW to 40 MW or more, depending on confinement assumptions, and either ICRF or ECRF heating, or both, will be used. 12 refs., 6 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400; AC02-76CH03073
• OSTI ID: 6999831
• Report Number(s): CONF-881015-40; IAEA-CN--50/G-2-1; ON: DE90011706
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101 -- Fusion Energy-- Plasma Research-- Confinement
Heating
&amp; Production
700200* -- Fusion Energy-- Fusion Power Plant Technology
AXIAL SYMMETRY
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
DIVERTORS
ECR HEATING
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
ICR HEATING
MHD EQUILIBRIUM
PERFORMANCE
PLASMA HEATING
POWER DENSITY
SYMMETRY
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS