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U.S. Department of Energy
Office of Scientific and Technical Information

TFTR remote maintenance

Conference ·
OSTI ID:5256756

The Tokamak Fusion Test Reactor (TFTR) is the first tokamak designed to utilize tritium plasmas and achieve significant neutron yields. Tritium operations are scheduled for the early 1980's at the Princeton Plasma Physics Laboratory. Complex operations of unprecedented scale must be performed remotely. The design of TFTR and the maintenance system supporting it are developing in parallel. The nature of the problem and a proposed set of maintenance tools are described.

Research Organization:
Princeton Univ., N.J. (USA). Plasma Physics Lab.
DOE Contract Number:
EY-76-C-02-3073
OSTI ID:
5256756
Report Number(s):
CONF-771117-4
Country of Publication:
United States
Language:
English