... and deteriorated heat transfer. The effects of the pressure, pipe diameter, mass flow rate, heat flux and flow direction also have been well studied in the experiments. From the perspective of theory, the pseudo-boiling theory noticed the similarities between the subcritical boiling and the supercritical fluid...

... Abstract This paper presents the assessment of the computational fluid dynamics (CFD) methodology for simulating the boiling flow in the Pressurized Water Reactor (PWR) rod bundle. The method includes the Eulerian-Eulerian two-fluid model coupled with the improved wall heat partitioning model...

... Abstract The visual experiment of subcooled flow boiling is performed in a vertical square channel with one heating rod for water. The objective is to investigate the vapor-liquid interface fluctuation characteristics to reveal the trigger mechanism of subcooled flow boiling critical heat flux...

... Abstract When the dry region on the high-temperature wall is cooled down by liquid, the dry region is transformed into wet region as the temperature shifts in a short time. Vigorous boiling occurs during the temperature transition. Especially, it is called the rewetting phenomenon that liquid...

... Abstract We investigated a single droplet impinging on an inclined heated wall with different inclination angles. A high-speed camera was used to observe this impinging process at 10000 frames / second. The phenomena of the droplet spreading, shrinking, rebounding, boiling, break-up...

... after the Fukushima Daiichi accident. The differences of thermophysical properties such as density, dynamic viscosity, and surface tension, between deionized water and seawater play an important role in the heat transfer. In addition, different boiling behaviors exhibit in the boiling process for two...

... within the Eulerian-Eulerian two-fluid model framework are assembled and extended to a general boiling formulation to deliver prediction of DNB at reactor conditions. The classic heat flux partitioning approach is advanced through selection of optimal closures for interaction length scale, nucleation...

... 23 02 2010 Copyright © 2009 by ASME Proceedings of the 17th International Conference on Nuclear Engineering ICONE17 July 12-16, 2009, Brussels, Belgium ICONE17-75738 STUDY ON SUBCOOLED FLOW BOILING HEAT TRANSFER UNDER VIBRATION CONDITIONS Hiroyasu Ohtake, Naoki Uchida and Yasuo Koizumi...

... 09 07 2009 Boiling heat transfer experiments were performed by using ethanol as test fluid. A heat transfer surface was at the bottom wall of the flow channel. Two types of experiments were conducted; horizontal-rectangular-narrow flow channel experiments and horizontal-narrow-flat...

... 09 07 2009 Onset of nucleate boiling — ONB — and critical heat flux — CHF — on subcooled flow boiling under oscillatory flow and vibration conditions, focusing on liquid velocity, amplitude and frequency of oscillation and vibration were investigated experimentally. Experiments were...

... 05 03 2009 Water single-phase and nucleate boiling heat transfer were experimentally investigated in vertical annuli with narrow gaps. The experimental data about water single-phase flow and boiling two-phase flow heat transfer in narrow annular channel were accumulated by two test...

... empirical findings is reiterated. steam generator fretting vibration boiling th o o tr b c th is r Proceedings of ICONE12 12th International Conference on Nuclear Engineering April 25-29, 2004, Arlington, Virginia USA -49059 As a tube accelerates toward a flexible AVB, e local pressure...