Maintenance concept development for the Compact Ignition Tokamak

Conference · Fri Jan 01 04:00:00 EST 1988

OSTI ID:6342722

Macdonald, D

The Compact Ignition Tokamak (CIT), located at the Princeton Plasma Physics Laboratory, will be the next major experimental machine in the US Fusion Program. Its use of deuterium-tritium (D-T) fuel requires the use of remote handling technology to carry out maintenance operations on the machine. These operations consist of removing and repairing such components as diagnostic equipment modules by using remotely operated maintenance equipment. The major equipment being developed for maintenance external to the vacuum vessel includes both bridge-mounted and floor-mounted manipulator systems. Additionally, decontamination (decon) equipment, hot cell repair facilities, and equipment for handling and packaging solid radioactive waste (rad-waste) are being developed. Recent design activities have focused on establishing maintenance system interfaces with the facility design, developing manipulator system requirements, and using mock-ups to support the tokamak configuration design. 3 refs., 8 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6342722
• Report Number(s): CONF-890304-27; ON: DE89004914
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
EQUIPMENT
LABORATORY EQUIPMENT
MAINTENANCE
MANAGEMENT
MANIPULATORS
MATERIALS HANDLING EQUIPMENT
RADIOACTIVE WASTE MANAGEMENT
REMOTE HANDLING EQUIPMENT
ROBOTS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
WASTE MANAGEMENT