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Title: Remote maintenance of Compact Ignition Tokamak ex-vessel systems

Conference ·
OSTI ID:5590975

The use of deuterium-tritium (D-T) fuel in the Compact Ignition Tokamak (CIT) will require applying remote handling technology for ex-vessel maintenance and replacement of machine components. Highly activated and contaminated components of the fusion device's auxiliary systems, such as diagnostics and RF heating, must be replaced using remotely operated maintenance equipment in the test cell. Throughout the CIT remote maintenance (RM) studies conducted to date, computer modeling has been used extensively to investigate manipulator access in these complex, tightly packed, and cluttered surroundings. A recent refinement of computer modeling involves the use of an intelligent engineering work station for realtime interactive display of task simulations. This paper discusses the use of three-dimensional (3-D) kinematic computer models of the CIT machines that are proving to be powerful tools in our efforts to evaluate RM requirements. This presentation includes a video-taped simulation of remote replacement of a plasma viewing assembly. The simulation illustrates some of the constraints associated with typical RM activities and the ways in which computer modeling enhances the design process. 1 ref., 3 figs.

Research Organization:
Oak Ridge National Lab., TN (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5590975
Report Number(s):
CONF-891007-20; ON: DE90001637; TRN: 89-029106
Resource Relation:
Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
Country of Publication:
United States
Language:
English