Design concept for the FED poloidal field coils using an internally cooled cable superconductor

Technical Report · Sat Jan 01 04:00:00 EST 1983

DOI:https://doi.org/10.2172/6653169· OSTI ID:6653169

Srivastava, V. C.

A description is given of the conceptual electromagnetic design for the central solenoid and ring coils of the Fusion Engineering Device (FED) employing force-cooled conductors. These coil designs use an internally cooled cable superconductor (ICCS) and appear to be feasible to meet the FED requirements. An innovative manifolding design concept that minimizes the space requirement is proposed. The force-cooled ohmic heating (OH) solenoid is designed to operate at 8 T. These coils do not require leak-tight helium vessels, which are difficult to design. The overall current density (including the structural support) is higher for the concept employing ICCS conductor than for the reference concept employing the pool-boiling conductor.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6653169
• Report Number(s): ORNL/TM-8474; ON: DE83005153
• Country of Publication: United States
• Language: English

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
COOLING
DESIGN
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
HEATING
JOULE HEATING
MAGNET COILS
MAGNETS
PLASMA HEATING
REFRIGERATION
RESISTANCE HEATING
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS