Maintainability features of the Compact Ignition Tokamak

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5576560

Spampinato, P T; Bushnell, C W

The compact ignition tokamak (CIT) is a deuterium-tritium (D-T) device envisaged to be the next experimental reactor in the US Fusion Program. The reactor will initially operate in a nonactivated hydrogen phase for approx. 2 yr. This will permit verification of the integrity of the total system and allow hands-on repair to equipment that has experienced shakedown and early operation failures. Once D-T operations commence, reactor maintenance will require remote handling techniques. An evaluation has been completed to determine what maintenance operations must be performed on the CIT. A maintenance philosophy has been developed that is based on the use of manipulator systems and robotics in the test cell. Replacement of life-limited equipment will be accomplished using a modular design approach for components, with simple remotely operable interfaces.

• Research Organization: Oak Ridge National Lab., TN
• OSTI ID: 5576560
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
EQUIPMENT
FIRST WALL
MAINTENANCE
MATERIALS HANDLING EQUIPMENT
REMOTE HANDLING EQUIPMENT
REMOTE VIEWING EQUIPMENT
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
VACUUM SYSTEMS