TSC disruption-induced forces on the CIT 1. 75 m vacuum vessel and internal coils

Conference · Wed Dec 31 23:00:00 EST 1986

OSTI ID:5333746

Sayer, R O; Jardin, S C; Strickler, D J

This paper discusses a critical CIT design issue: vacuum vessel (VV) safety margin relative to loads arising from VV eddy currents induced by plasma motion and current decay during disruptions. The motivation if this study is needed to perform disruption simulations which would provide time histories of the VV currents required for detailed engineering load and stress analyses. Calculation of the time evolution of forces on the VV and on the internal coils and the analysis of the effects of plasma current decay rate, initial beta value, and plasma trajectories are discussed. Also discussed is simulation model, VV results and internal coil results. 8 figs., 2 tabs.

• Research Organization: Princeton Univ., NJ (USA). Plasma Physics Lab.
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5333746
• Report Number(s): CONF-871272-1-Vugraphs; ON: DE88006179
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700102 -- Fusion Energy-- Plasma Research-- Diagnostics
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700202 -- Fusion Power Plant Technology-- Magnet Coils & Fields
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
CONTAINERS
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
MAGNET COILS
PLASMA DISRUPTION
PLASMA SIMULATION
PRESSURE VESSELS
SIMULATION
STRESS ANALYSIS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
TRAJECTORIES