Toroidal field coil system of the Oak Ridge EPR reference design

Conference · Thu Jan 01 00:00:00 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; TRN: 76-022772
• Resource Relation: Conference: Applied superconductivity conference, Stanford, CA, USA, 17 Aug 1976
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
SUPERCONDUCTING MAGNETS
DESIGN
TOKAMAK TYPE REACTORS
NIOBIUM ALLOYS
SHAPE
TIN ALLOYS
TITANIUM ALLOYS
ALLOYS
CONFIGURATION
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
SUPERCONDUCTING DEVICES
THERMONUCLEAR REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields
420201 - Engineering- Cryogenic Equipment & Devices