INTOR toroidal field coil design studies
Conference
·
· IEEE Trans. Magn.; (United States)
OSTI ID:6481964
Preliminary design considerations for a toroidal field coil for INTOR with trapezoidal winding cross section, 11 T maximum field, and 2.35 ka/cm/sup 2/ current density in the winding are presented. Due to severe restrictions imposed by the INTOR specifications meeting the allowable stress level is a big challenge for the designer. INTOR refers to the International Tokamak Reactor Experiment. 3 refs.
- Research Organization:
- Kernforschungszent Karlsruhe, Germany, F.R.
- OSTI ID:
- 6481964
- Report Number(s):
- CONF-810340-
- Conference Information:
- Journal Name: IEEE Trans. Magn.; (United States) Journal Volume: MAG-17:5
- Country of Publication:
- United States
- Language:
- English
Similar Records
Design and analysis of the INTOR toroidal field-coil structural system
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FED/INTOR critical issues assessment of toroidal field coil options
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5991834
Superconducting poloidal field coil studies for INTOR
Conference
·
Wed Dec 31 23:00:00 EST 1980
· Proc. Symp. Eng. Probl. Fusion Res.; (United States)
·
OSTI ID:6420818
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Technical Report
·
Sun Oct 31 23:00:00 EST 1982
·
OSTI ID:6614460
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
ANNULAR SPACE
CONFIGURATION
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
INTOR TOKAMAK
MAGNET COILS
MECHANICAL STRUCTURES
SPACE
STRESSES
SUPPORTS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
ANNULAR SPACE
CONFIGURATION
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
INTOR TOKAMAK
MAGNET COILS
MECHANICAL STRUCTURES
SPACE
STRESSES
SUPPORTS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION