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Tokamak Fusion Core Experiment (TFCX) special-purpose remote maintenance systems

Conference ·
OSTI ID:5981757
;
A key element in the preconceptual design of the Tokamak Fusion Core Experiment (TFCX) was the development of design concepts for special-purpose remote maintenance systems. Included were systems for shield sector replacement, vacuum vessel sector and toroidal field coil replacement, limiter blade replacement, protective tile replacement, and general-purpose maintenance. This paper addresses these systems as they apply to the copper toroidal field (TF) coil version of the TFCX.
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
5981757
Report Number(s):
EGG-M-22084; CONF-850310-33; ON: DE85008039
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
LIMITERS
MAGNET COILS
MAINTENANCE
MATERIALS HANDLING EQUIPMENT
REMOTE HANDLING EQUIPMENT
SHIELDING
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS