Critical-Heat-Flux Experiment on the Screw Tube under One-Sided-Heating Conditions

Author:

Araki Masanori1,Sato Kazuyoshi1,Suzuki Satoshi1,Akiba Masato1

Affiliation:

1. Japan Atomic Energy Research Institute Naka-Fusion Research Establishment, 801-1, Naka-machi Naka-gun, Ibaraki-ken, 311-01 Japan

Publisher

Informa UK Limited

Subject

General Engineering

Reference9 articles.

1. W. R. Gambill, R. D. Bundy, and R. W. Wansbrough, “Heat Transfer, Burnout and Pressure Drop for Water in Swirl Flow Through Tubes with Internal Twisted Tapes,” ORNL-2911, Oak Ridge National Laboratory (1960).

2. J. A. Paterson, G. Koehler, and R. P. Wells, “The Design of Multi-Megawatt Actively Cooled Beam Dumps for the Neutral Beam Engineering Facility,” Chicago, Illinois, October 26–29, 1981, p. 1666, American Nuclear Society (1981).

3. Burnout Experiment in Subcooled Forced-Convection Boiling of Water for Beam Dumps of a High Power Neutral Beam Injector

4. S. L. Milora, S. K. Combs, and C. A. Foster, “A Numerical Model for Swirl Flow Cooling in High Heat Flux Particle Beam Targets and the Design of a Swirl Flow Based Plasma Limiter,” ORNL-TM-9183, Oak Ridge National Laboratory (1986).

5. J. A. Koski, A. G. Beattie, J. B. Whitley, and C. D. Croessmann, “Experimental Verification of Subcooled Flow Boiling for Tokamak Pump Limiter Design,” 87-HT-45, American Society of Mechanical Engineers (1987).

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