Void fraction in simulated BWR fuel assembly. (I). Evaluation of cross-sectional averaged void fraction

Shinichi Morooka, Takao Ishizuka, Tatsuo Kagawa, Kunihiro Yoshimura

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

Void measurement of a vertical (4×4) rod bundle has been conducted in a steam-water two phase flow using an advanced X-ray CT scanner and 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 could be correlated by the Drift Flux model and that Zuber Findlay correlation made it possible to appropriately predict the void data. However, this correlation underestimates data for a higher void fraction region. This is because the flow pattern applicable range for Z-F correlation is not appropriate to this experimental range. Therefore, the new void correlation was developed based on the authors' data.

Original languageEnglish
Pages (from-to)925-932
Number of pages8
JournalNippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan
Volume30
Issue number10
Publication statusPublished - 1988 Oct
Externally publishedYes

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Void fraction
Two phase flow
Flow patterns
Steam
Fluxes
X rays
Water

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Void fraction in simulated BWR fuel assembly. (I). Evaluation of cross-sectional averaged void fraction. / Morooka, Shinichi; Ishizuka, Takao; Kagawa, Tatsuo; Yoshimura, Kunihiro.

In: Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, Vol. 30, No. 10, 10.1988, p. 925-932.

Research output: Contribution to journalArticle

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