Void fraction in simulated BWR fuel assembly, (II) spacer effect on void fraction and analysis without cross-flow

Shinichi Morooka, Kenetsu Shirakawa, Takao Ishizuka, Kunihiro Yoshimura, Katsuhiko Mawatari

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Abstract

Void measurement of a vertical 4×4 rod bundle has been calculated behind a spacer in a steam-water two-phase flow using an advanced X-ray CT scanner and one-dimensional single subchannel analysis without a cross-flow was done. It was found from the experimental results that the cross-sectional averaged void fraction data behind the spacer could be predicted by the drift-flux model, that the spacer has a negligible effect on the cross-sectional averaged void fraction and that EPRI correlation made it possible to accurately predict the void data. In addition, the simplified single subchannel analysis without the cross-flow between subchannels gave good agreement with data of center subchannels in a quality range of 5% or more. However, the analysis predicted higher void fraction than experimental results in the corner subchannel.

Original languageEnglish
Pages (from-to)585-593
Number of pages9
JournalNippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan
Volume33
Issue number6
Publication statusPublished - 1991 Jun
Externally publishedYes

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ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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