Experience in Experimental Validation of the Steam Generators Used in NPP with Fast Reactors

The main results of trials conducted with different models of steam generators for purposes of validating the steam generators used in reactor facilities with sodium and lead as liquid-metal coolants are presented. On the basis of these trials, suggestions were made concerning the operating conditions, viz. the required superheating of the steam in the evaporator of the BN-600 reactor in order to prevent the removal of moisture and the working pressure in the evaporator of the BN-350 reactor in order to prevent unstable regimes, data were obtained on thermodynamic nonequilibrium and heat exchange in the transcritical zone of a sodium-heated steam-generating tube, the bounds of the stable operating regimes of the Field channel were determined, and it was shown that reversal of the circulation does not occur for one of the possible variants of a steam generator in the BREST-OD-300 reactor setup.