Toroidal field coil system of the Oak Ridge EPR reference design

Conference · Thu Jan 01 04:00:00 EST 1976

OSTI ID:7146974

Lue, J W; Luton, J N

A refined design of the toroidal field (TF) coil system for the Oak Ridge Tokamak Experimental Power Reactor (EPR) study is presented. This design is based on cable conductor cooled by force-flow supercritical helium. It uses superconducting multifilamentary Nb/sub 3/Sn for a maximum design field of 11 T at the coil windings. A hybrid system which uses NbTi at low field regions is recommended. The coil structure consists of stainless steel segments welded together to form a continuous stiff honeycomb. Conductor optimization and stability analysis specifically applicable to the forced-flow cooled conductors are given.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7146974
• Report Number(s): CONF-760829-7
• 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
ALLOYS
CONFIGURATION
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
NIOBIUM ALLOYS
SHAPE
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TIN ALLOYS
TITANIUM ALLOYS
TOKAMAK TYPE REACTORS