Overview of the compact ignition tokamak
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; TRN: 88-018620
- Resource Relation:
- Conference: 14. SOFT - symposium on fusion technology, Avignon, France, 8 Sep 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPACT IGNITION TOKAMAK
DESIGN
COST
DIVERTORS
FIRST WALL
ICR HEATING
LIMITERS
MAGNET COILS
PRESSURE VESSELS
REACTOR FUELING
CLOSED PLASMA DEVICES
CONTAINERS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
HEATING
HIGH-FREQUENCY HEATING
PLASMA HEATING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology