Experimental study on void fraction in a simulated BWR fuel assembly (evaluation of cross-sectional averaged void fraction)

Shinichi Morooka, Takao Ishizuka, Masaru Iizuka, Kunihiro Yoshimura

Research output: Contribution to journalArticle

47 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)91-98
Number of pages8
JournalNuclear Engineering and Design
Volume114
Issue number1
DOIs
Publication statusPublished - 1989 May 2
Externally publishedYes

Fingerprint

Void fraction
void
bundles
voids
rods
experimental study
assembly
evaluation
Steam
two phase flow
Two phase flow
steam
scanners
Fluxes
X rays
scanner
Water
water flow
water
x rays

ASJC Scopus subject areas

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

Cite this

Experimental study on void fraction in a simulated BWR fuel assembly (evaluation of cross-sectional averaged void fraction). / Morooka, Shinichi; Ishizuka, Takao; Iizuka, Masaru; Yoshimura, Kunihiro.

In: Nuclear Engineering and Design, Vol. 114, No. 1, 02.05.1989, p. 91-98.

Research output: Contribution to journalArticle

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