TY - JOUR
T1 - Experimental study on void fraction in a simulated BWR fuel assembly (evaluation of cross-sectional averaged void fraction)
AU - Morooka, Shinichi
AU - Ishizuka, Takao
AU - Iizuka, Masaru
AU - Yoshimura, Kunihiro
PY - 1989/5/2
Y1 - 1989/5/2
N2 - Void fraction measurement of a vertical (4 x 4) rod bundle has been conducted in a steam-water two phase flow, using an advanced X-ray CT scanner. A large amount of rod bundle data was obtained. It was found from the results that the cross-sectional averaged void fraction data for a rod bundle can be correlated by the Drift-Flux model and that the Zuber-Findlay correlation underestimates the data in a void fraction area of 80% or more. This is because the data range over which this correlation was developed, does not cover this experimental range. Therefore, a modified correlation was developed based on the authors' data.
AB - Void fraction measurement of a vertical (4 x 4) rod bundle has been conducted in a steam-water two phase flow, using an advanced X-ray CT scanner. A large amount of rod bundle data was obtained. It was found from the results that the cross-sectional averaged void fraction data for a rod bundle can be correlated by the Drift-Flux model and that the Zuber-Findlay correlation underestimates the data in a void fraction area of 80% or more. This is because the data range over which this correlation was developed, does not cover this experimental range. Therefore, a modified correlation was developed based on the authors' data.
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U2 - 10.1016/0029-5493(89)90128-3
DO - 10.1016/0029-5493(89)90128-3
M3 - Article
AN - SCOPUS:0006069359
VL - 114
SP - 91
EP - 98
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
IS - 1
ER -