A study of the two-phase natural circulation flow through the annular gap between a reactor vessel and insulation system

2004 ◽  
Vol 31 (1) ◽  
pp. 43-52 ◽  
Author(s):  
K.S. Ha ◽  
R.J. Park ◽  
H.Y. Kim ◽  
S.B. Kim ◽  
H.D. Kim
Keyword(s):  
Natural Circulation ◽  
Reactor Vessel ◽  
Circulation Flow ◽  
Insulation System ◽  
Two Phase ◽  
Annular Gap ◽  
Flow Through

Loop analysis of a natural circulation two-phase flow under an external reactor vessel cooling

2008 ◽  
Vol 35 (8) ◽  
pp. 1001-1006 ◽  
Author(s):  
Jae Cheol Kim ◽  
Kwang Soon Ha ◽  
Rae Joon Park ◽  
Sang Baik Kim ◽  
Seong Wan Hong
Keyword(s):  
Two Phase Flow ◽  
Natural Circulation ◽  
Reactor Vessel ◽  
Phase Flow ◽  
Loop Analysis ◽  
Two Phase

scholarly journals Single Phase Natural Circulation Flow through Solar Evacuated Tubes Collectors on the Equatorial Zone

2015 ◽  
Vol 75 ◽  
pp. 467-472 ◽  
Author(s):  
Celso Recalde ◽  
Cesar Cisneros ◽  
Carlos Avila ◽  
Washington Logroño ◽  
Mayra Recalde
Keyword(s):  
Single Phase ◽  
Natural Circulation ◽  
Equatorial Zone ◽  
Circulation Flow ◽  
Flow Through ◽  
Evacuated Tubes

Two-Phase Natural Circulation Cooling Performance Assessment and Safety Analysis for APR1400 Core Catcher System

2014 ◽  
Author(s):  
Ki Won Song ◽  
Shripad T. Revankar ◽  
Hyun Sun Park ◽  
Bo Rhee ◽  
Kwang Soon Ha ◽  
...  
Keyword(s):  
Void Fraction ◽  
Flow Rate ◽  
Natural Circulation ◽  
Scaling Analysis ◽  
Circulation Flow ◽  
Two Phase ◽  
Cooling Performance ◽  
The Core ◽  
Core Catcher ◽  
Circulation Flow Rate

The two-phase natural circulation cooling performance of the APR1400 core catcher system is studied utilizing a drift flux flow model developed via scaling analysis and with an air-water experimental facility. Scaling analysis was carried out to identify key parameters, so that model facility could simulates two-phase natural circulation. In the experimental apparatus, instead of steam, air is injected into the top wall of the test channel to simulate bubble formation and void distribution due to boiling water in the core catcher channel. Measurement of void fraction critical to the heat transfer between the wall and coolant is carried out at certain key position using double-sensor conductivity probes. Results from the model provide expected natural circulation flow rate in the cooling channel of the core catcher system. The observed flow regimes and the data on void fraction are presented. For a given design of the down comer piping entrance condition bubble entrainment was observed that significantly reduced the natural circulation flow rate.

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