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Void fraction in simulated BWR fuel assembly. (I). Evaluation of cross-sectional averaged void fraction
BWR模擬燃料集合体内のボイド率 I 断面平均ボイド率についての評価
1988
Journal of the Atomic Energy Society of Japan
BWR模擬燃料集合体内のボイド率 I 断面平均ボイド率についての評価
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
doi:10.3327/jaesj.30.925
fatcat:bcylymraljgchnou5ilg56spia