Design of the TFTR presents special engineering problems as a result of constraints posed by the physics requirements of the fusion experiments. The ratio of plasma major and minor radii and the associated magnetic field strength required to achieve desired plasma conditions, the required confinement time, the two-component plasma concept, the complications of providing shielding from the 14 MeV neutrons and the necessity to control the inventory of tritium fuel, all constitute problems which, often, in actuality, must be approached as materials problems. The complex, precision structures must satisfy various criteria, for example, low magnetic permeability, high electrical resistivity, resistance to neutron activation and high damage tolerance. Another constraint in the engineering design of TFTR is the requirement to optimize access to machine components for maintenance and repair. Many of the problems associated with accessibility have been resolved: the vacuum vessel has been designed as a ten-segment vessel; the igloo shielding of the machine is composed of interlocking blocks of boron-loaded concrete; the center column is designed in three segments. Current engineering emphasis is on finalizing design of the toroidal field coils, lower poloidal field coils, vacuum vessel liners and limiters, and peripheral systems such as the vacuum pumping system and arrangement of diagnostics.
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July 1978
This article was originally published in
Journal of Engineering for Power
Research Papers
Special Engineering Problems of TFTR
D. E. Lee
D. E. Lee
Princeton Plasma Physics Laboratory, Princeton, N. J.
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D. E. Lee
Princeton Plasma Physics Laboratory, Princeton, N. J.
J. Eng. Power. Jul 1978, 100(3): 417-423 (7 pages)
Published Online: July 1, 1978
Article history
Received:
August 2, 1977
Online:
July 14, 2010
Citation
Lee, D. E. (July 1, 1978). "Special Engineering Problems of TFTR." ASME. J. Eng. Power. July 1978; 100(3): 417–423. https://doi.org/10.1115/1.3446373
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