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U.S. Department of Energy
Office of Scientific and Technical Information

Maintainability features of the compact ignition tokamak

Conference ·
OSTI ID:5789084

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 approximately two years. This will permit verification of the integrity of the total system and allow hands-on repair to equipment which 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 which is based upon 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. Examples of operations to be done remotely include: (1) replacing of rf antennae and Faraday shields, (2) uncoupling diagnostic and fueling penetrations, (3) removing of all port covers, and (4) replacing first wall armor tiles, optical mirrors, and vacuum windows.

Research Organization:
Oak Ridge National Lab., TN (USA); Princeton Univ., NJ (USA). Plasma Physics Lab.
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5789084
Report Number(s):
CONF-860610-22; ON: DE86007332
Country of Publication:
United States
Language:
English