Morozov A.V., Kalyakin D.S., Ragulin S.V., Sakhipgareev A.R., Soshkina A.S., Shlepkin A.S.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
The results of the experimental study of thermal-hydraulic processes in the passive safety systems of the VVER reactor of new generation are presented in the paper. The experiments were carried out on the model experimental test facilities built in IPPE. The processes through which interaction occurs between the opposite flows of saturated steam and cold water moving in the vertical steam line of the additional system for passively flooding the core fromthe second-stage hydro accumulators are studied. The specific features of undeveloped boiling of liquid on a single horizontal tube heated by steam
and steam-gas mixture that is typical for of the condensation operating mode of a VVER reactor steam generator are investigated.
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