Next tokamak facility
Conference
·
· Nucl. Technol./Fusion; (United States)
OSTI ID:6263938
Design studies on a superconducting, long-pulse, current-driven, ignited tokamak, called the Toroidal Fusion Core Demonstration (TFCD), are being conducted by the Fusion Engineering Design Center (FEDC) and Princeton Plasma Physics Laboratory (PPPL) with additional broad community involvement. Options include the use of allsuperconducting toroidal field (TF) coils, a superconducting-copper hybrid arrangement of TF coils, or all-copper TF coils. Only the first two options have been considered to date. The general feasibility of these approaches has been established with the goal of high performance (ignition, about390 MW; wall loading about2.2 MW/m/sup 2/) at minimum capital cost. The preconceptual effort will be completed in early FY 1984 and a selection made from the indicated options. The TFCD is judged to represent a reasonable necessary step between the Tokamak Fusion Test Reactor (TFTR) and the Engineering Test Reactor (ETR).
- Research Organization:
- Princeton Plasma Physics Lab., Princeton Univ., P.O. Box 451, Princeton, NJ 08540
- OSTI ID:
- 6263938
- Report Number(s):
- CONF-830406-
- Conference Information:
- Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
ANNULAR SPACE
COMPOSITE MATERIALS
CONFIGURATION
COPPER
CURRENT-DRIVE HEATING
DEMONSTRATION PROGRAMS
DESIGN
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
ELEMENTS
EQUIPMENT
FEASIBILITY STUDIES
HEATING
JOINT VENTURES
JOULE HEATING
MAGNET COILS
MATERIALS
METALS
PERFORMANCE TESTING
PLASMA HEATING
POWER DENSITY
POWER RANGE 1-10 MW
POWER RANGE 100-1000 MW
PULSED FUSION REACTORS
PULSED MAGNET COILS
RESISTANCE HEATING
SPACE
SUPERCONDUCTING COILS
SUPERCONDUCTING COMPOSITES
TESTING
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION
TRANSITION ELEMENTS
WALL LOADING
700200* -- Fusion Energy-- Fusion Power Plant Technology
ANNULAR SPACE
COMPOSITE MATERIALS
CONFIGURATION
COPPER
CURRENT-DRIVE HEATING
DEMONSTRATION PROGRAMS
DESIGN
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
ELEMENTS
EQUIPMENT
FEASIBILITY STUDIES
HEATING
JOINT VENTURES
JOULE HEATING
MAGNET COILS
MATERIALS
METALS
PERFORMANCE TESTING
PLASMA HEATING
POWER DENSITY
POWER RANGE 1-10 MW
POWER RANGE 100-1000 MW
PULSED FUSION REACTORS
PULSED MAGNET COILS
RESISTANCE HEATING
SPACE
SUPERCONDUCTING COILS
SUPERCONDUCTING COMPOSITES
TESTING
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION
TRANSITION ELEMENTS
WALL LOADING