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

*この研究の対応する著者

研究成果: Article査読

64 被引用数 (Scopus)

抄録

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.

本文言語English
ページ(範囲)91-98
ページ数8
ジャーナルNuclear Engineering and Design
114
1
DOI
出版ステータスPublished - 1989 5月 2
外部発表はい

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学
  • 土木構造工学
  • 機械工学
  • 安全性、リスク、信頼性、品質管理

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