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Home / Publications / Journals / Fusion Science and Technology / Volume 4 / Number 2P2

Next Tokamak Facility

J. A. Schmidt, C. A. Flanagan

Fusion Science and Technology / Volume 4 / Number 2P2 / September 1983 / Pages 56-61

U.S. Next-Generation Tokamak and Tandem Mirror Programs / dx.doi.org/10.13182/FST83-A22845

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, ∼390 MW; wall loading ∼2.2 MW/m2) 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).

 
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