Ex-vessel remote maintenance design for the Compact Ignition Tokamak
Conference
·
OSTI ID:5972812
The use of deuterium-tritium (D-T) fuel for operation of the Compact Ignition Tokamak (CIT) imposes a requirement for remote handling technology to carry out maintenance operations on auxiliary machine components. These operations consist of removing and repairing components such as diagnostics and radio frequency (rf) heating modules using remotely operated maintenance equipment. The major equipment that is being developed to accomplish maintenance external to the plasma chamber includes the bridge-mounted manipulator system for test cell operations, decontamination (decon) equipment, hot cell equipment, and solid rad-waste handling equipment. Wherever possible, the project will use commercially available equipment. Several areas of the maintenance system design have been addressed in fiscal year (FY) 1987. These included conceptual designs of manipulator systems, the start of a remote equipment research and development (R and D) program, and definition of the hot cell, decon, and equipment repair facility requirements. The manipulator work included investigating transporters and viewing/lighting subsystems. In each case, existing commercial units are being assessed initially, along with viable alternative approaches. R and D work also included demonstrations of remote handling operations on full-size, partial mock-ups of the CIT machine at the Oak Ridge National Laboratory (ORNL) Remote Operations and Maintenance Development Facility.
- Research Organization:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center; Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5972812
- Report Number(s):
- CONF-871007-4; ON: DE88000581
- Country of Publication:
- United States
- Language:
- English
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Ex-vessel remote maintenance for the Compact Ignition Tokamak
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Ex-vessel remote maintenance design for the Compact Ignition Tokamak
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Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6729106
Maintenance concept development for the Compact Ignition Tokamak
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Thu Dec 31 23:00:00 EST 1987
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OSTI ID:6342722
Ex-vessel remote maintenance design for the Compact Ignition Tokamak
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·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5589310
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
EQUIPMENT
FUELS
LABORATORY EQUIPMENT
MAINTENANCE
MANIPULATORS
MATERIALS HANDLING EQUIPMENT
REMOTE HANDLING
REMOTE HANDLING EQUIPMENT
REPAIR
THERMONUCLEAR DEVICES
THERMONUCLEAR FUELS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
EQUIPMENT
FUELS
LABORATORY EQUIPMENT
MAINTENANCE
MANIPULATORS
MATERIALS HANDLING EQUIPMENT
REMOTE HANDLING
REMOTE HANDLING EQUIPMENT
REPAIR
THERMONUCLEAR DEVICES
THERMONUCLEAR FUELS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS