Structural behavior of the Bitter plate tf magnet for the Zephyr ignition test reactor

Conference · Thu Jan 01 00:00:00 EST 1981 · Proc. Symp. Eng. Probl. Fusion Res.; (United States)

OSTI ID:6421020

Bobrov, E S; Becker, H

This paper discusses methods and results of the computer structural analysis of the Bitter plate toroidal field magnet design for the ZEPHYR Ignition Test Reactor. The magnet provides a field of 7.06 T at the center of the bore which is 1.76 m from the major toroidal axis. The ignited plasma is located at a major radius of 1.36 m where the magnetic field is 9.11 T. The plasma is moved to this final position following compression in the major radius. The horizontal bore of the magnet is 1.8 m.

• Research Organization: MIT, Cambridge, MA, USA
• OSTI ID: 6421020
• Report Number(s): CONF-811040-; TRN: 83-007939
• Journal Information: Proc. Symp. Eng. Probl. Fusion Res.; (United States), Conference: 9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SUPERCONDUCTING MAGNETS
MECHANICAL STRUCTURES
STRESS ANALYSIS
TOKAMAK TYPE REACTORS
DESIGN
FINITE ELEMENT METHOD
TOROIDAL CONFIGURATION
ANNULAR SPACE
CONFIGURATION
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
NUMERICAL SOLUTION
SPACE
SUPERCONDUCTING DEVICES
THERMONUCLEAR REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields