Experimental modelling of eddy currents and deflection for tokamak limiters
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6905815
During plasma disruptions in a tokamak fusion reactor, eddy currents are induced in the limiters and other conducting structures surrounding the plasma. Interactions between these currents with the toroidal field causes deflection and stress in the structural components. The structural motion in the strong magnetic field induces additional eddy current opposing the initial eddy current and modifying subsequent structural dynamics. Therefore, the motion and current are coupled and must be solved simultaneously. The coupling between current and deflection in cantilevered beams was investigated experimentally. The beams provide a simple model for the limiter blade of a tokamak fusion reactor. Several test pieces and various magnetic field conditions were employed to study the extend of the coupling effect from weak to strong coupling. Experimental results are compared with analytical predictions.
- Research Organization:
- Argonne National Lab., 9700 South Cass Avenue, Argonne, IL 60439
- OSTI ID:
- 6905815
- Report Number(s):
- CONF-860652-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experimental modeling of eddy currents and defections for tokamak limiters
Experimental modeling of eddy currents and deflections for tokamak limiters
Experimental study of coupling between eddy currents and deflections in cantilevered beams as models of tokamak limiters
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6764763
Experimental modeling of eddy currents and deflections for tokamak limiters
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5497152
Experimental study of coupling between eddy currents and deflections in cantilevered beams as models of tokamak limiters
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:7012093
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ANNULAR SPACE
CONFIGURATION
COUPLING
CURRENTS
DATA ANALYSIS
DYNAMICS
EDDY CURRENTS
ELECTRIC CURRENTS
LIMITERS
MAGNETIC FIELDS
MATHEMATICAL MODELS
MECHANICS
PLASMA DISRUPTION
RESEARCH PROGRAMS
SPACE
STRESSES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ANNULAR SPACE
CONFIGURATION
COUPLING
CURRENTS
DATA ANALYSIS
DYNAMICS
EDDY CURRENTS
ELECTRIC CURRENTS
LIMITERS
MAGNETIC FIELDS
MATHEMATICAL MODELS
MECHANICS
PLASMA DISRUPTION
RESEARCH PROGRAMS
SPACE
STRESSES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TOROIDAL CONFIGURATION