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

Conference · · Fusion Technol.; (United States)
OSTI ID:6011665
;

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, ID
OSTI ID:
6011665
Report Number(s):
CONF-850310-
Journal Information:
Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 8:1; ISSN FUSTE
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
INSTALLATION
LIMITERS
MAGNET COILS
MAINTENANCE
REMOTE HANDLING
REMOVAL
SHIELDS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VACUUM SYSTEMS