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AbstractAbstract
[en] Princeton University Plasma Physics Laboratory (PPPL) is constructing a Tokamak Fusion Test Reactor (TFTR) scheduled to begin operation for fusion research experiments in late 1981, first with hydrogen and deuterium plasmas and later, in the second phase, using tritium for high power fusion studies. This latter mode will introduce considerable complexity to operation and maintenance of the TFTR in terms of meeting requirements for tritium handling, adequate radiation shielding, and corrective and preventive maintenance procedures. In this paper we discuss plans for the installation and preoperational testing of the major subsystems of TFTR, proposed start-up and operating scenarios for the device and the system of operational control. In addition, the TFTR Maintenance Plan and related procedures for specific major maintenance tasks are described, including the use of remote handling equipment and remote manipulators. Each of these topics is addressed in terms of the current status of planning and development
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Powell, J.R.; Eterno, C.T. (eds.); American Nuclear Society, NM. Trinity Section; American Nuclear Society. Div. of Controlled Nuclear Fusion; Department of Energy, Washington, DC (USA). Div. of Magnetic Fusion Energy; Electric Power Research Inst., Palo Alto, CA (USA); p. 1016-1025; 1978; p. 1016-1025; 3. meeting on the technology of controlled thermonuclear fusion; Santa Fe, NM, USA; 9 - 11 May 1978
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