Driven-current tokamak (DCT) scoping study

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:5860833

Reid, R L

The present Department of Energy (DOE) plan calls for the construction of an Engineering Test Reactor (ETR) that is to be the last major experimental fusion device prior to the commercialization of fusion power. The plasma driver of the ETR is to be either a long-pulse tokamak or a tandem mirror machine. The possibility of using the Tokamak Fusion Test Reactor (TFTR) facility to consolidate the physics and technology database for the tokamak version of the ETR has been considered. This paper addresses two of the options being considered: (1) a superconducting toroidal field (TF) coil-hydrogen plasma alternative, and (2) a superconducting or hybrid TF coil-high Q alternative. Both options assume essentially steady-state operation through the application of rf current drive. The options are evaluated on the basis of performance and cost determined by application of the Fusion Engineering Design Center (FEDC) Tokamak System Code.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5860833
• Report Number(s): CONF-830406-99; ON: DE83017183
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
COST
CURRENT-DRIVE HEATING
DESIGN
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
EQUIPMENT
HEATING
HYDROGEN
JOULE HEATING
MAGNETS
NONMETALS
PLASMA HEATING
RESISTANCE HEATING
SPECIFICATIONS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS