Published July 1985
| Version v1
Journal article
Tokamak Fusion Core Experiment (TFCX) special-purpose remote maintenance systems
Description
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
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 8
- Journal Issue
- 1
- Series
- Fusion Technol.
- Journal Page Range
- 314-317
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 6. topical meeting on the technology of fusion energy.
- Dates
- 3-7 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17080156
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LIMITERS; MAGNET COILS; MAINTENANCE; REMOTE HANDLING; SEPARATION PROCESSES; SHIELDS; SPECIFICATIONS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; VACUUM SYSTEMS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES
Optional Information
- Secondary number(s)
- CONF-850310--.