DocumentCode
2040753
Title
Remote maintenance of Compact Ignition Tokamak ex-vessel systems
Author
DePew, R.E. ; Macdonald, D.
Author_Institution
Central Eng., Oak Ridge Nat. Lab., TN, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
593
Abstract
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 workstation for real-time interactive display of task simulations. Three-dimensional (3-D) kinematic computer models of the CIT machines are proving to be powerful tools in evaluating RM requirements. The use of the models is discussed
Keywords
computerised materials handling; fusion reactor theory and design; nuclear engineering computing; nuclear reactor maintenance; robots; telecontrol; CIT remote maintenance; Compact Ignition Tokamak; RF heating; auxiliary systems; computer modeling; diagnostics; ex-vessel maintenance; intelligent engineering workstation; manipulator access; real-time interactive display; remote-handling technology; remotely operated maintenance equipment; task simulations; Computer displays; Fuels; Heating; Ignition; Machine components; Machine intelligence; Power engineering computing; Radio frequency; System testing; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102289
Filename
102289
Link To Document