inverted annular film boiling
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2018 ◽  
Vol 14 ◽  
pp. 49
Author(s):  
Daniel Vlček ◽  
Vojtěch Caha ◽  
Martin Ševeček

This paper deals with Post-CHF (critical heat flux) heat transfer with the focus on different regimes of film boiling. The new thermal-hydraulic code TUBE 2.0 is presented. This code uses the equation of energy conservation and predefined correlations to establish wall temperature, the departure of nucleate boiling ratio as well as other parameters of cooling in a simple geometry - an isolated channel. With experimental data of inverted annular film boiling from Stewart, the best-performing correlation for calculation of post-CHF heat transfer in the channel was determined. Finally, the new presented code TUBE 2.0 and subchannel code SUBCAL owned by Chemcomex a.s. are compared using results of various experiments conducted by Becker. Data from Stewart could not be used because of inability to predict the onset of boiling crisis with several correlations.


2015 ◽  
Vol 190 (3) ◽  
pp. 301-312 ◽  
Author(s):  
L. Mohanta ◽  
M. P. Riley ◽  
F. B. Cheung ◽  
S. M. Bajorek ◽  
J. M. Kelly ◽  
...  

Author(s):  
Seok Cho ◽  
Sang-Ki Moon ◽  
Ki-Yong Choi ◽  
Se-Young Chun ◽  
Moon-Ki Chung ◽  
...  

A series of bottom reflood tests were carried out to investigate thermal-hydraulic characteristics during the reflood phase. This paper includes descriptions of three related groups of reflood tests categorized by the geometry of a flow channel and an electric power shape of heater rods. A centrally-heated annular geometry with an outer-visualizing tube was adopted for the first two groups of tests (group-A and -B), and a 6×6 rod bundle geometry for the other group of tests (group-C). The ranges of experimental parameters are 2∼8 cm/s of flooding velocity, 20∼80 °C of inlet subcooling temperature, and 500∼700 °C of initial wall temperature. In the single rod annular flow channel reflood test, quench front behavior can be easily observed through the visualizing window and a dominant flow regime near downstream of quench front is inverted annular film boiling regardless of the flooding velocity. For the case of the 6×6 rod bundle experiments, on the other hand, the dominant flow regime is dispersed flow film boiling (DFFB), and therefore the thermal hydraulic behavior becomes more complicated and chaotic due to the interaction between liquid phase such as droplet and liquid film and vapor phase generated from liquid-wall heat transfer.


1997 ◽  
Vol 40 (11) ◽  
pp. 2655-2670 ◽  
Author(s):  
N. Hammouda ◽  
D.C. Groeneveld ◽  
S.C. Cheng

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