Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

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