Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Ex-vessel remote maintenance design for the Compact Ignition Tokamak

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5589310
The use of deuterium-tritium (D-T) fuel for operation of the Compact Ignition Tokamak (CIT) imposes a requirement for remote handling technology for ex-vessel maintenance operations on auxiliary machine components. These operations consist of repairing and replacing components such as diagnostic, radio-frequency (rf) heating, and fueling systems using remotely operated maintenance equipment in the test cell. In addition, ex-vessel maintenance design also includes developing hot cell facilities for equipment decontamination, repair, and solid radioactive waste handling. The test cell maintenance philosophy is markedly influenced by the neutron/gamma shield surrounding the machine that allows personal access into the test cell one day after shutdown. Hence, maintenance operations can be performed hands-on in the test cell with the shield intact and must be remotely performed when the shield is disassembled for machine access. The constricted access to the auxiliary components of the machine affect the design requirements for the maintenance equipment and impose major spatial constraints. Several major areas of the maintenance system design are being addressed in fiscal year 1987. These include conceptual design of the manipulator system, preliminary remote equipment research and development, and definition of the hot cell, decontamination, and equipment repair facility requirements. The manipulator work includes investigating transporters and viewing/lighting subsystems. 2 figs.
Research Organization:
Grumman, Oak Ridge, TN (USA)
OSTI ID:
5589310
Report Number(s):
CONF-8711195-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
Country of Publication:
United States
Language:
English