A simple delay model for two-phase flow dynamics

Conference · Fri Sep 01 00:00:00 EDT 1995

OSTI ID:111458

Clausse, A; Delmastro, D F; Juanico`, L E ^[1]

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1. Centro Atomico Bariloche (Argentina)

A model based in delay equations for density-wave oscillations is presented. High Froude numbers and moderate ones were considered. The equations were numerically analyzed and compared with more sophisticated models. The influence of the gravity term was studied. Different kinds of behavior were found, particularly sub-critical and super-critical Hopf bifurcations. Moreover the present approach can be used to better understand the complicated dynamics of boiling flows systems.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; American Nuclear Society (ANS), La Grange Park, IL (United States); American Institute of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers (ASME), 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: 111458
• Report Number(s): NUREG/CP-0142-Vol.4; CONF-950904-Vol.4; ON: TI95017080; TRN: 95:021646
• Resource Relation: Conference: 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24; Block, R.C.; Feiner, F. [American Nuclear Society, La Grange Park, IL (United States)]; PB: 825 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
TWO-PHASE FLOW
MATHEMATICAL MODELS
REACTOR CHANNELS
FROUDE NUMBER
HEAT TRANSFER
HYDRAULICS
OSCILLATIONS
TWO-DIMENSIONAL CALCULATIONS