TIBER-II TF (toroidal-field) winding pack design
The superconducting, toroidal-field (TF) coils in the Tokamak Ignition/Burn Engineering Reactor (TIBER II) are designed with cable-in-conduit conductor (CICC) using Nb/sub 3/Sn composite strands. To design the CICC winding pack, we used an optimization technique that maximizes the conductor stability without violating the constraints imposed by the structure, electrical insulation, quench protection, and fabrication technique. Detailed helium-properties codes calculate the heat removal along a flow path, and detailed field calculations determine the temperature, current, and stability margins. The conductor sheath is designed as distributed structure to partially support the combined in-plane and out-of-plane loads generated within the winding pack. Pancakes of the coil are wound, reacted, and insulated before being potted in the case. This design is aggressive but fully consistent with good engineering practice. 5 refs., 4 figs., 2 tabs.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5705106
- Report Number(s):
- UCRL-96862; CONF-871007-84; ON: DE88004408
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
ALLOYS
DESIGN
ELECTRICAL EQUIPMENT
ELECTRICAL INSULATORS
EQUIPMENT
MAGNETIC FIELDS
NIOBIUM ALLOYS
OPTIMIZATION
PERFORMANCE
SUPERCONDUCTING COILS
THERMONUCLEAR REACTORS
TIBER-X TOKAMAK
TOKAMAK TYPE REACTORS