Design improvments to simplify the remote maintenance of tokamaks

Conference · Sun Jan 01 04:00:00 EST 1978 · Conf. Remote Syst. Technol., Proc.; (United States)

OSTI ID:6737700

Spampinato, P T ^[1]; Sardella, C; Shannon, T E

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1. Grumman Aerospace Corp., Bethpage, NY

By the nature of its plasma confinement concept, the tokamak is a difficult device to maintain; maintainability problems are compounded by the need to perform all operations remotely. Modifications to the Oak Ridge National Laboratory baseline, the next step (TNS), which led to significant improvements in device maintainability, are discussed. These modifications are: a reduction in the number of toroidal field coils used and an increase in coil size; a rearrangement of poloidal field coils to preclude the need for coil dismantling during a torus sector replacement; and use of a secondary vacuum enclosure. Various types of secondary enclosures are discussed and the rationale for selecting a vacuum building approach is given.

• OSTI ID: 6737700
• Report Number(s): CONF-7811120-
• Conference Information: Journal Name: Conf. Remote Syst. Technol., Proc.; (United States) Journal Volume: 26
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
CONTAINMENT
CONTAINMENT BUILDINGS
EQUIPMENT
MAINTENANCE
MATERIALS HANDLING EQUIPMENT
REACTOR MAINTENANCE
REMOTE HANDLING EQUIPMENT
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS