TSC (Tokamak Simulation Code) disruption scenarios and CIT (Compact Ignition Tokamak) vacuum vessel force evolution
The Tokamak Simulation Code and the TWIR postprocessor code have been used to develop credible plasma disruption scenarios for the Compact Ignition Tokamak (CIT) in order to predict the evolution of forces on CIT conducting structures and to provide results required for detailed structural design analysis. The extreme values of net radial and vertical vacuum vessel (VV) forces were found to be F{sub R}={minus}12.0 MN/rad and F{sub Z}={minus}3.0 MN/rad, respectively, for the CIT 2.1-m, 11-MA design. Net VV force evolution was found to be altered significantly by two mechanisms not noted previously. The first, due to poloidal VV currents arising from increased plasma paramagnetism during thermal quench, reduces the magnitude of the extreme F{sub R} by 15-50{percent} and modifies the distribution of forces substantially. The second effect is that slower plasma current decay rates give more severe net vertical VV loads because the current decay occurs when the plasma has moved farther from midplane than is the case for faster decay rates. 7 refs., 9 figs., 1 tab.
- Research Organization:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7225236
- Report Number(s):
- ORNL/FEDC-89/3; ON: DE90008087
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700103* -- Fusion Energy-- Plasma Research-- Kinetics
700107 -- Fusion Energy-- Plasma Research-- Instabilities
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
PLASMA DISRUPTION
PLASMA SIMULATION
PRESSURE VESSELS
SIMULATION
T CODES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS