The Tokamak fusion core experiment study
Conference
·
OSTI ID:1024776
- Princeton Plasma Physics Laboratory (PPPL)
- ORNL
The basic objective of the next major step in the US fusion program has been defined as the achievement of ignition and long pulse equilibrium burn of a fusion plasma in the Tokamak Fusion Core Experiment (TFCX) device. Preconceptual design studies have seen completion of four candidate versions to provide the comparative information needed to narrow down the range of TFCX options before proceeding to the conceptual design phase. All four designs share the same objective and conform to common physics, engineering and costing criteria. The four base options considered differed mainly in the toroidal field coil design, two employing superconducting coils and the other two copper coils. In each case (copper and superconducting), one relatively conventional version was carried as well as a version employing more exotic toroidal field coil design assumptions. Sizes range from R = 2.6 m for the smaller of the two copper versions to R = 4.08 m for the larger superconducting option. In all cases, the plasma current was about 10 MA and the toroidal field about 4 T.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- SC USDOE - Office of Science (SC)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1024776
- Country of Publication:
- United States
- Language:
- English
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