Thermal analysis of the TFTR vacuum vessel wall protective plate
The TFTR vacuum vessel is to be protected with tungsten plates from the effects of neutral beam impingement. A thermal analysis is performed to determine the maximum allowable beam intensity (power per unit area) under normal and faulted operating conditions. In order to permit a faulted pulse, or unattenuated injection, to occur after normal pulse series, the maximum neutral beam energy flux should be below 10 kW/cm/sup 2/ depending on the beam design configuration, to prevent the melting of the plates. The analyses were performed using an injection time of 0.5 second and a cycle time of 300 seconds.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Fusion Power Systems Dept.
- DOE Contract Number:
- EY-76-C-02-3073
- OSTI ID:
- 5318739
- Report Number(s):
- WFPS-TME-015; TRN: 78-001359
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TFTR DEVICE
SHIELDING
THERMONUCLEAR REACTOR WALLS
THERMODYNAMIC PROPERTIES
NEUTRAL ATOM BEAM INJECTION
PLATES
SAFETY
TUNGSTEN
VACUUM SYSTEMS
BEAM INJECTION
CLOSED PLASMA DEVICES
ELEMENTS
METALS
PHYSICAL PROPERTIES
REFRACTORY METALS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSITION ELEMENTS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
TFTR DEVICE
SHIELDING
THERMONUCLEAR REACTOR WALLS
THERMODYNAMIC PROPERTIES
NEUTRAL ATOM BEAM INJECTION
PLATES
SAFETY
TUNGSTEN
VACUUM SYSTEMS
BEAM INJECTION
CLOSED PLASMA DEVICES
ELEMENTS
METALS
PHYSICAL PROPERTIES
REFRACTORY METALS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSITION ELEMENTS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing