Thermal and mechanical analysis of the Faraday shield for the Compact Ignition Tokamak
The antenna for the ion cyclotron resonance heating (ICRH) system of the Compact Ignition Tokamak (CIT) is protected from the plasma environment by a Faraday shield, an array of gas-cooled metallic tubes. The plasma side of the tubes is armored with graphite tiles, which can be either brazed or mechanically attached to the tube. The Faraday shield has been analyzed using finite element codes to model thermal and mechanical responses to typical CIT heating and disruption loads. Four representative materials (Inconel 718, tantalum-10 tungsten, copper alloy C17510, and molybdenum alloy TZM) and several combinations of tube and armor thicknesses were used in the thermal analysis, which revealed that maximum allowable temperatures were not exceeded for any of the four materials considered. The two-dimensional thermal stress analysis indicated Von Mises stresses greater than twice the yield stress for a tube constructed of Inconel 718 (the original design material) for the brazed-graphite design. Analysis of stresses caused by plasma disruption ()rvec J) )times) )rvec B)) loads eliminated the copper and molybdenum alloys as candidate tube materials. Of the four materials considered, tantalum-10 tungsten performed the best for a brazed graphite design, showing acceptable thermal stresses (69% of yield) and disruption stresses (42% of yield). A preliminary thermal analysis of the mechanically attached graphite scheme predicts minimal thermal stresses in the tube. The survivability of the graphite tubes in this scheme is yet to be analyzed. 8 refs., 19 figs., 2 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5181389
- Report Number(s):
- ORNL/FEDC-87/5; ON: DE88007855
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPACT IGNITION TOKAMAK
THERMAL SHIELDS
STRESS ANALYSIS
THERMAL ANALYSIS
ANTENNAS
FINITE ELEMENT METHOD
GRAPHITE
ICR HEATING
PLASMA DISRUPTION
TANTALUM ALLOYS
TEMPERATURE EFFECTS
THERMONUCLEAR REACTOR MATERIALS
ALLOYS
CARBON
CLOSED PLASMA DEVICES
ELECTRICAL EQUIPMENT
ELEMENTAL MINERALS
ELEMENTS
EQUIPMENT
HEATING
HIGH-FREQUENCY HEATING
MATERIALS
MINERALS
NONMETALS
NUMERICAL SOLUTION
PLASMA HEATING
SHIELDS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700201 - Fusion Power Plant Technology- Blanket Engineering
700101 - Fusion Energy- Plasma Research- Confinement
Heating
& Production