Grabezhnaya V.A., Mikheyev A.S.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
One of the promising areas for the development
of large-scale power engineering is the creation of nuclear power plants with fast
reactors. The NPP high energy parameters also require an increase in the
parameters of the water circuit. It is necessary to increase both the pressure of the output
steam and its flow rate to obtain a higher efficiency of the station. In the developed projects of reactor plants, steam generators (SG)
of integral design are considered. Any SG design requires experimental
justification both in terms of confirming the design parameters for steam, and
in terms of thermal hydraulics of the steam generating channel. In once-through steam generators under a
certain combination of operating parameters (power, pressure, temperature, feed
water flow rate), self-sustaining oscillations in the flow rate of the working
fluid, the so-called hydrodynamic instability, can be observed. Density-wave
oscillation instabilities lead to a non-stationary crisis of heat transfer. A
lot of work is devoted to the experimental finding the instability thresholds,
most of which was carried out on models with steam-generating tubes in the form
of coiled channels.
This paper presents the results of tests of various models of steam-generating channels,
which were carried out in IPPE at the SPRUT facility, for the occurrence of
thermohydraulic instability. The effect of length of the steam generating straight
tube on the length of wall temperature oscillations zone is shown. The stabilizing effect of vortex flows (coiled channel or tube with
internal fins) on thermal-hydraulic stability is noted.
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