An experimental study on rewetting phenomena in transient conditions of bwrs

Sakae Muto*, Takafumi Anegawa, Shinichi Morooka, Seiichi Yokobori, Yukio Takigawa, Shigeo Ebata, Yuichiro Yoshimoto, Shuzi Suzuki

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

20 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)311-321
Number of pages11
JournalNuclear Engineering and Design
Issue number2-3
Publication statusPublished - 1990 Jun 2
Externally publishedYes

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality


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