Overview of the compact ignition tokamak

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:5153119

Flanagan, C A

A national team has developed a baseline concept for a Compact Ignition Tokamak (CIT). The CIT mission is to achieve ignition and provide experimental capability to study the behavior of burning plasma. The design uses large magnetic fields on axis (about 10 T) and large plasma currents (about 9-10 MA). The magnet structure derives high strength from the use of a copper-Inconel composite plate design in the nose of region of the toroidal field (TF) coil and in the ohmic heating solenoid. Inertial cooling is used;liquid nitrogen temperatures are established at the beginning of each pulse. Capability is provided to operate either with a divertor or limiter based plasma. The design is very compact (1.32-m major radius, 0.43-m plasma radius), has 16 TF coils, and has 16 major horizontal access ports, about 30 cm by 80 cm, located between TF coils. The schedule is for a construction project to be authorized for the period FY 1988-93.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5153119
• Report Number(s): CONF-860917-12-FP; ON: DE88007440
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
CONTAINERS
COST
DESIGN
DIVERTORS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
FIRST WALL
HEATING
HIGH-FREQUENCY HEATING
ICR HEATING
LIMITERS
MAGNET COILS
PLASMA HEATING
PRESSURE VESSELS
REACTOR FUELING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS