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Tokamak Fusion Core Experiment (TFCX) Special-Purpose Remote Maintenance Systemsa

L. S. Masson, H. J. Welland

Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 314-317

Operation and Maintenance / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40063

A key element in the preconceptual design of the Tokamak Fusion Core Experiment (TFCX) was the development of design concepts for special-purpose remote maintenance systems. Included were systems for shield sector replacement, vacuum vessel sector and toroidal field coil replacement, limiter blade replacement, protective tile replacement, and general-purpose maintenance. This paper addresses these systems as they apply to the copper toroidal field (TF) coil version of the TFCX.