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TPX remote maintenance and shielding

Journal Article · · Fusion Technology
OSTI ID:41430
;  [1]
  1. Oak Ridge National Lab., TN (United States)
The Tokamak Physics Experiment (TPX) machine design incorporates comprehensive planning for efficient and safe component maintenance. Three programmatic decisions have been made to insure the successful implementation of this objective. First, the tokamak incorporates radiation shielding to reduce activation of components and limit the dose rate to personnel working on the outside of the machine. This allows most of the ex-vessel equipment to be maintained through conventional {open_quotes}hands-on{close_quotes} procedures. Second, to the maximum extent possible, low activation materials will be used inside the shielding volume. This resulted in the selection of Titanium (Ti-6Al-4V) for the vacuum vessel and Plasma Facing Components (PFC) structures. The third decision stipulated that the primary in-vessel components will be replaced or repaired via remote maintenance tools specifically provided for the task. The component designers have been given the responsibility of incorporating maintenance design and for proving the maintainability of the design concepts in full-scale mockup tests prior to the initiation of final fabrication. Remote maintenance of the TPX machine is facilitated by general purpose tools provided by a special purpose design team. Major tools will include an in-vessel transporter, a vessel transfer system and a large component transfer container. In addition, tools such as manipulators and remotely operable impact wrenches will be made available to the component designers by this group. Maintenance systems will also provide the necessary controls for this equipment.
DOE Contract Number:
AC05-84OR21400; AC02-76CH03073
OSTI ID:
41430
Report Number(s):
CONF-940630--
Journal Information:
Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 26; ISSN 0748-1896; ISSN FUSTE8
Country of Publication:
United States
Language:
English

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