Abstract: A method and apparatus is shown for establishing a predetermined concentration of gas in the reactor core coolant for a pressurized water nuclear power system. Gas is added to core coolant water in a bubble column. The gas-water mixture flows through static mixers in the column to produce the desired gas concentration in the water.

Abstract: An arrangement for the emergency cooling of the steam generator unit is of a pressurized-water nuclear power plant is disclosed. Steam is passed through a blow-off pipe (11) into a closed vessel (14) having a water space (12) and a gas space (13). A nest of heat exchanger tubes (15) extends through the water space (12) in a heat transfer relationship to cool the water space. Steam is dumped under emergency conditions into the vessel via a steam distributor nozzle (18) operatively connected at the end of the blow-off pipe and is condensed in the water space. The steam distributor nozzle is arranged essentially below and to the side of the nest of heat exchanger tubes to enhance mixing heat transfer. The resulting condensate is returned to the steam generator as condensate.

Abstract: A gas charging device injects hydrogen into the pressurized water that cools the core of a nuclear power reactor through nozzles provided in a pressurized water flow pump. Conduit and valve combinations also are provided to permit solid matter to be flushed from the nozzles.