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Critical heat flux modeling in water pool boiling during power transients
Affiliation:1. Mechanical Engineering Department, UNET, San Cristóbal 5001, Venezuela;2. ETSII/Universidad Politécnica de Madrid, J. Gutiérrez Abascal, 2-28006 Madrid, Spain;1. University of New Mexico, 1 University of New Mexico, Albuquerque, NM 87131, United States;2. Shanghai Jiao Tong University, 1954 Huashan Rd, Shanghai 200000, China;3. Pennsylvania State University, Old Main, State College, PA 16802, United States;4. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831, United States;5. University of Pittsburgh, 4200 Fifth Avenue, Pittsburgh, PA 15260, United States;6. Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83402, United States;1. Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Room 24–206, 77 Massachusetts Avenue, Cambridge, MA 02139-4307, USA;2. Nuclear Reactor Laboratory, 138 Albany Street, Massachusetts Institute of Technology, Cambridge, MA 02139, USA
Abstract:This article suggests a method of the determination of main parameters and dynamic characteristics of heat transfer crisis on a surface of fast heated wall. The new physical models describing process of transition from nucleate to film boiling are presented. The results of transient critical heat flux modeling are compared with the experimental data for saturated water pool boiling under atmospheric pressure.
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