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.
|ジャーナル||Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan|
|出版物ステータス||Published - 1988 10|
ASJC Scopus subject areas
- Nuclear Energy and Engineering