Burnout experiment in subcooled forced-convection boiling of water for beam dumps of a high power neutral beam injector
Experimental studies were made on burnout heat flux in highly subcooled forced-convection boiling of water for the design of beam dumps of a high power neutral beam injector for Japan Atomic Energy Research Institute Tokamak-60. These dumps are composed of many circular tubes with two longitudinal fins. The tube was irradiated with nonuniformly distributed hydrogen ion beams of 120 to 200 kW for as long as 10 s. The coolant water was circulated at flow velocities of 3 to 7.5 m/s at exit pressures of 0.4 to 0.9 MPa. The burnout and film-boiling data were obtained at local heat fluxes of 8 to 15 MW/m/sup 2/. These values were as high as 2.5 times larger than those for the circumferentially uniform heat flux case with the same parameters. These data showed insensitivity to local subcooling as well as to pressure, and simple burnout correlations were derived. From these results, the beam dumps have been designed to receive energetic beam fluxes of as high as 5 MW/m/sup 2/ with a margin of a factor of 2 for burnout.
- Research Organization:
- Japan Atomic Energy Research Institute, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-ken
- OSTI ID:
- 5537482
- Journal Information:
- Nucl. Technol./Fusion; (United States), Vol. 2:4
- Country of Publication:
- United States
- Language:
- English
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Subcooled water flow boiling experiments under uniform high heat flux conditions
Related Subjects
TOKAMAK TYPE REACTORS
BURNOUT
REACTOR SAFETY EXPERIMENTS
ACCELERATOR FACILITIES
BEAM DUMPS
DESIGN
FORCED CONVECTION
HEAT FLUX
NEUTRAL ATOM BEAM INJECTION
PRESSURE MEASUREMENT
SUBCOOLED BOILING
BEAM INJECTION
BOILING
CONVECTION
PHASE TRANSFORMATIONS
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology