First wall and vacuum vessel analysis for Compact Ignition Tokamaks
This paper describes the ongoing analysis efforts supporting the design of the first wall (FW) and vacuum vessel (VV) components for the Compact Ignition Tokamak (CIT). Thermal and stress analyses of FW graphite tiles have established a nominal tile thickness of 1.0 cm and a maximum allowable FW surface heat flux of 11.0 MW/m/sup 2/. Calculations have shown that for a cooldown time of one hour, the required tile to VV thermal conductance is > 0.1 W/K. Estimates of worst-case electromagnetic loads and resulting stresses on the VV during plasma disruptions have shown the maximum stress levels to be below the allowable limits for the VV material. These results demonstrate that the selected FW/VV concept is consistent with the design objectives.
- Research Organization:
- TRW Inc., One Space Park, Redondo Beach, CA 90278
- OSTI ID:
- 7190757
- Report Number(s):
- CONF-860652-
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 10:3; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
CARBON
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
COOLING
DESIGN
DIMENSIONS
ELECTROMAGNETIC RADIATION
ELEMENTAL MINERALS
ELEMENTS
FIRST WALL
GRAPHITE
HEAT FLUX
MINERALS
NONMETALS
PHYSICAL PROPERTIES
PLASMA DISRUPTION
RADIATIONS
STRESS ANALYSIS
THERMAL ANALYSIS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
THICKNESS
TIME DEPENDENCE
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
VACUUM SYSTEMS