Configuration development and structural assessment of the FEDC ignitor concept

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:5794577

Brown, T G; Lee, V D; Mayhall, J

Emphasis has been placed on the configuration design of the reactor core module and the external, hydraulic preload system. An elevation view of the FEDC Ignitor concept highlighting the reactor core and the external preload system is shown. The reactor core was designed to allow the fit-up of the toroidal field (TF) coils to meet the requirements of TF wedging, bucking (or the combination of both). The TF coil outboard leg was sized to carry its own in-plane loads; the inboard TF leg was sized to carry the residual tension load (after subtracting preload) plus the wedging/bucking loads. Preload is applied directly to the inboard leg at the top of the device, through an insulation compression block. The outboard half of the TF coil is enclosed in a steel case to support out-of-plane loads. In-plane gaps between the coil and case allow in-plane expansion due to thermal and mechanical loads.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5794577
• Report Number(s): CONF-860610-20; ON: DE86007303
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
MAGNET COILS
MECHANICAL STRUCTURES
SIZE
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS