Next tokamak facility

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

OSTI ID:6073946

Schmidt, J A; Flanagan, C A

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 all-superconducting 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, approx. 390 MW; wall loading approx. 2.2 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 Univ., NJ (USA). Plasma Physics Lab.; Westinghouse Electric Corp., Oak Ridge, TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6073946
• Report Number(s): CONF-830406-83; ON: DE83014216
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
FEASIBILITY STUDIES
MAGNETS
PERFORMANCE
PLANNING
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS