TY - JOUR
T1 - An experimental study on rewetting phenomena in transient conditions of bwrs
AU - Muto, Sakae
AU - Anegawa, Takafumi
AU - Morooka, Shinichi
AU - Yokobori, Seiichi
AU - Takigawa, Yukio
AU - Ebata, Shigeo
AU - Yoshimoto, Yuichiro
AU - Suzuki, Shuzi
PY - 1990/6/2
Y1 - 1990/6/2
N2 - It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.
AB - It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.
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U2 - 10.1016/0029-5493(90)90383-9
DO - 10.1016/0029-5493(90)90383-9
M3 - Article
AN - SCOPUS:0000442940
SN - 0029-5493
VL - 120
SP - 311
EP - 321
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
IS - 2-3
ER -