Internally Cooled Cable Superconductor (ICCS) for TF and PF coils of FED
Conference
·
OSTI ID:5651647
Internally Cooled Cable Superconductor (ICCS) concepts developed for TF and PF coils of FED are described. These concepts represent one of the options for FED, and other conductor concepts are still being explored, i.e., no decision has been made for the conductor concepts to be utilized for FED. The TF coil conductor design is based on an ICCS successfully used in a small test magnet at ORNL. The conductor consists of triplets of NbTi strands loosely packed in a stainless steel conduit similar to the Westinghouse LCP coil. The operating current for the conductor is 25.5 kA at l0T and 3.1/sup 0/K. The conductor is co-wound with a stainless steel C-shaped channel to provide a direct load path to the coil case for the accumulated magnetic loads in the winding. The strand diameter in the conductor is optimized to reduce the eddy current losses. The nuclear heating in the winding is the most dominant heat load. In order to remove these heat loads due to nuclear heating and ac losses in the winding, it is necessary to lower the inlet temperature of helium to 2.2/sup 0/K. The conductor has a thermal capacity of approx. 200 mJ/cc, which provides a comfortable stability margin under the operating conditions.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5651647
- Report Number(s):
- CONF-821108-32; ON: DE84003365
- Country of Publication:
- United States
- Language:
- English
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Internally cooled cable superconductor (ICCS) for TF and PF coils of FED
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Journal Article
·
Sun May 01 00:00:00 EDT 1983
· IEEE Trans. Magn.; (United States)
·
OSTI ID:5509708
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Thu Feb 28 23:00:00 EST 1985
· IEEE Trans. Magn.; (United States)
·
OSTI ID:6331764
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Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6401966
Related Subjects
420201 -- Engineering-- Cryogenic Equipment & Devices
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
ALLOYS
COOLING
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
NIOBIUM ALLOYS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TITANIUM ALLOYS
TOKAMAK TYPE REACTORS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
ALLOYS
COOLING
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
NIOBIUM ALLOYS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TITANIUM ALLOYS
TOKAMAK TYPE REACTORS