Void fraction distribution in a heated rod bundle under flow stagnation conditions
Conference
·
OSTI ID:111429
- Centro Atomico Bariloche and Instituto Balseiro, Bariloche (Argentina)
An experimental study was performed to determine the axial void fraction distribution along a heated rod bundle under flow stagnation conditions. The development of the flow pattern was investigated for different heat flow rates. It was found that in general the void fraction is overestimated by the Zuber & Findlay model while the Chexal-Lellouche correlation produces a better prediction.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
- OSTI ID:
- 111429
- Report Number(s):
- NUREG/CP--0142-Vol.4; CONF-950904--Vol.4; ON: TI95017080
- Country of Publication:
- United States
- Language:
- English
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