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An experimental study on rewetting phenomena in transient conditions of bwrs
Authors:Sakae Muto   Takafumi Anegawa   Shinichi Morooka   Seiichi Yokobori   Yukio Takigawa   Shigeo Ebata   Yuichiro Yoshimoto  Shuzi Suzuki
Affiliation:

a Tokyo Electric Power Company, Japan

b Toshiba Corporation, Japan

c Nippon Atomic Industry Group Co. Ltd., Japan

d Hitachi Ltd., Japan

e Hitachi Engineering Co. Ltd., Japan

Abstract: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.
Keywords:
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