Authors & Affiliations
Kuzina Yu.A., Sorokin A.P., Denisova N.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Kuzina Yu.A. – Director of Nuclear Energetic Department, Cand. Sci. (Tech.). Contacts: 1, Bondarenko sq., Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-86-63; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.).
Denisova N.A. – Lead Engineer, A.I. Leypunsky Institute for Physics and Power Engineering.
Abstract
The results of experimental studies on an
integral water model of the temperature fields and the flow structure of a
non-isothermal primary coolant in the sodium-cooled fast neutron reactor in
various regimes: forced circulation, during the transition to the decay heat
removal and decay heat removal with natural
convection of the coolant are presented in the article. It is
shown, that under the influence of lift forces on the non-isothermal coolant
flow in the upper chamber of the reactor at the periphery of its bottom region over the side shields, a
stable cold coolant isothermal zone is formed, whose dimensions increase with
increase of total water flow rate. An essential and stable coolant temperature
stratification was detected in the peripheral area of the upper (hot) chamber
over the side shields, in the cold and pressure chambers, in the elevator
baffle, in the cooling system of the reactor vessel, and in the outlet of
intermediate and autonomous heat exchangers in different operating regimes.
Large gradients and temperature fluctuations are registered at the interface of
stratified and recycling formations. In all studied cool down versions, the
coolant temperature at the outlet from the heads of the core fuel assembly is
decreased and the coolant temperature in the peripheral zone of the upper
chamber is increased as compared to the forced circulation. High efficiency of
a passive decay heat removal system of high-power fast reactor with submersible
autonomous heat exchangers is confirmed. Thus, in a
normal operation regime, even in case of malfunction of three submersible
autonomous heat exchangers, the temperature of the equipment inside the reactor
remains within acceptable limits and decay heat removal from the reactor does
not exceed safe operation limits. The obtained results can be used for computer
code verification and for approximate estimate of the reactor plant parameters on
the similarity criteria basis.
Keywords
fast reactor, reactor tank, integral layout, submersible heat exchangers, experiment, thermal hydraulics, temperature stratification of the coolant, forced convection, natural convection, decay heat removal
Article Text (PDF, in Russian)
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UDC 621.039.516.25:621.039.526
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 1, 1:15
