The poloidal field coil system of the fusion engineering device
- ORNL
The authors examine the poloidal field (PF) system of the current Fusion Engineering Device (FED) configuration. Plasma shaping capabilities, cost evaluations, maintenance, and structural engineering considerations have led to a PF coil system consisting of a central OH solenoid, copper D-shaping coils internal to the toroidal field (TF) coils, and external superconducting coils providing the main equilibrium field. Numerical MHD equilibrium calcuations show that this PF configuration is consistent with the physics goals of the FED, i.e., high-beta operation ({beta} {approx} 5-6%) with a low safety factor (q {approx} 2.5-3.5) and impurity control using a pump limiter approach. The PF system modifications necessary for a poloidal divertor option are discussed. Through a sequence of equilibria, they simulate the time dependent current requirements and examine the PF interaction with the ohmic heating, equilibrium field, and plasma currents during the various stages of a typical FED discharge.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- SC USDOE - Office of Science (SC)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1024768
- Country of Publication:
- United States
- Language:
- English
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