Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Viewgraphs presented at the 7th topical meeting on the Technology of Fusion Energy are included. (MOW).
Maintainability Features of the Compact Ignition Tokamak
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Viewgraphs presented at the 7th topical meeting on the Technology of Fusion Energy are included. (MOW).
Maintenance Features of the Compact Ignition Tokamak Fusion Reactor
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Compact Ignition Tokamak (CIT) is envisaged to be the next experimental machine in the US Fusion Program. Its use of deuterium/tritium fuel requires the implementation of remote handling technology for maintenance and disassembly operations. The reactor is surrounded by a close-proximity nuclear shield which is designed to permit personnel access within the test cell, one day after shutdown. With the shield in place, certain maintenance activities in the cell may be done hands-on. Maintenance on the reactor is accomplished remotely using a boom-mounted manipulator after disassembling the shield. Maintenance within the plasma chamber is accomplished with two articulated boom manipulators that are capable of operating in a vacuum environment. They are stored in a vacuum enclosure behind movable shield plugs.
Energy Research Abstracts
Author: Fusion Energy Update
Author: REMOTE MAINTENANCE OF COMPACT IGNITION TOKAMAK EX-VESSEL SYSTEMS.
Author: R.E. DePEW.Physics Aspects of the Compact Ignition Tokamak
Author: Energy Research Abstracts
Author: Ex-vessel Remote Maintenance Design for the Compact Ignition Tokamak
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The use of deuterium-tritium (D-T) fuel for operation of the Compact Ignition Tokamak (CIT) imposes a requirement for remote handling technology to carry out maintenance operations on auxiliary machine components. These operations consist of removing and repairing components such as diagnostics and radio frequency (rf) heating modules using remotely operated maintenance equipment. The major equipment that is being developed to accomplish maintenance external to the plasma chamber includes the bridge-mounted manipulator system for test cell operations, decontamination (decon) equipment, hot cell equipment, and solid rad-waste handling equipment. Wherever possible, the project will use commercially available equipment. Several areas of the maintenance system design have been addressed in fiscal year (FY) 1987. These included conceptual designs of manipulator systems, the start of a remote equipment research and development (R and D) program, and definition of the hot cell, decon, and equipment repair facility requirements. The manipulator work included investigating transporters and viewing/lighting subsystems. In each case, existing commercial units are being assessed initially, along with viable alternative approaches. R and D work also included demonstrations of remote handling operations on full-size, partial mock-ups of the CIT machine at the Oak Ridge National Laboratory (ORNL) Remote Operations and Maintenance Development Facility.
Maintenance Concept Development for the Compact Ignition Tokamak
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Author: D. C. Keeton