Published April 1983 | Version v1
Journal article

Void fraction under high pressure, low flow conditions in rod bundle geometry

  • 1. Oak Ridge National Lab., TN (USA). Engineering Technology Div.
  • 2. Cornell Univ., Ithaca, NY (USA). Lab. of Nuclear Engineering

Description

Void-fraction data are reported from a series of high pressure, low heat and mass flux experiments. Testing was performed in a heated vertical rod bundle with internal dimensions similar to a PWR fuel bundle. The results are of interest in analyses of small break loss of coolant accidents. The experiments showed that, at a given pressure, void-fraction data could be fitted to a drift-flux equation with a constant drift-velocity. The drift-velocity was observed to decrease with increasing pressure and was independent of void fraction: a characteristic normally associated with churn-turbulent flow. However, relevant drift-flux correlations found in the literature gave relatively poor predictions of void fractions. The best predictions were obtained from an empirical correlation based on dimensional analyses. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
75
Journal Issue
1
Series
CODEN: NEDEA.;Nucl. Eng. Des.
Journal Page Range
99-108
ISSN
0029-5493

INIS

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