Design and analysis of the INTOR toroidal field-coil structural system

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:5991834

O'Toole, J A; Brown, T G; Shannon, T E

The International Tokamak Reactor (INTOR) is a unique collaborative effort among the USA, USSR, EURATOM, and Japan to define the characteristics and objectives of, assess the technical feasibility of, and develop a design for the next major experiment in the world-wide tokamak program. The conceptual design consists of twelve toroidal field (TF) coils, each having a bore of 7.75 X 10.7 meters and a maximum field of 10.8 Tesla. The all-external poloidal field (PF) coil system imposes a very large pulsed field on the TF coil system. The superconducting TF and PF coils are enclosed by a common vacuum cryostat which includes individual enclosures for each TF coil's outer leg. This configuration provides a large window through which a complete torus sector can be withdrawn. The purpose of this study was to develop a feasible TF coil structural system design. The various design criteria and their effects on the design are discussed. The rationale supporting the allowable cyclic stress of 200 MPa (29 ksi) is discussed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5991834
• Report Number(s): CONF-811040-81(Draft); ON: DE82002887
• 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
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
FEASIBILITY STUDIES
INTOR TOKAMAK
MAGNETS
STRESS ANALYSIS
STRESSES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS