Two-phase flow instabilities in a vertical annular channel

Technical Report · Fri Sep 01 04:00:00 EDT 1995

DOI:https://doi.org/10.2172/107758· OSTI ID:107758

Babelli, I.; Nair, S.; Ishii, M. ^[1]

---

1. Purdue Univ., West Lafayette, IN (United States)

An experimental test facility was built to study two-phase flow instabilities in vertical annular channel with emphasis on downward flow under low pressure and low flow conditions. The specific geometry of the test section is similar to the fuel-target sub-channel of the Savannah River Site (SRS) Mark 22 fuel assembly. Critical Heat Flux (CHF) was observed following flow excursion and flow reversal in the test section. Density wave instability was not recorded in this series of experimental runs. The results of this experimental study show that flow excursion is the dominant instability mode under low flow, low pressure, and down flow conditions. The onset of instability data are plotted on the subcooling-Zuber (phase change) numbers stability plane.

• 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: 107758
• Report Number(s): NUREG/CP--0142-Vol.2; CONF-950904--Vol.2; ON: TI95017078
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
CRITICAL HEAT FLUX
DIAGRAMS
EXPERIMENTAL DATA
FUEL ASSEMBLIES
HYDRAULICS
INSTABILITY
REACTOR SAFETY
SAVANNAH RIVER PLANT
TWO-PHASE FLOW