Conductors for tokamak toroidal field coils

Conference · Sat Jan 01 04:00:00 EST 1977

OSTI ID:5271565

Fietz, W A

This paper describes six conductors which are being developed for use in superconducting toroidal field coils of tokamak fusion machines. Included are three pool boiling and three forced flow concepts. Research and development programs on several of the conductors are under way, jointly involving Oak Ridge National Laboratory (ORNL) and conductor manufacturers. Conductors will be tested in short lengths and in the form of 3m x 2.5m Large Coil Segment (LCS) tests. The conductor development and testing is closely coordinated with the Large Coil Program (LCP) at ORNL.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5271565
• Report Number(s): CONF-771029-142
• 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
CABLES
CONDUCTOR DEVICES
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
PERFORMANCE TESTING
RESEARCH PROGRAMS
SUPERCONDUCTING CABLES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TEST FACILITIES
TESTING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS