Patent Number: 052176827
Section: abstract

A nuclear reactor system including a main heat transport path around which a first coolant is pumped by main circulation pumps to transport heat from the reactor core to a steam generator. A heat exchanger is located in the main heat transport path after the outlet from the steam generator, the secondary side of that heat exchanger being in a decay heat removal loop which contains a second liquid coolant. A vapor separator in the decay heat removal loop is connected to an outlet of the heat exchanger with the vapor separator's outlet being connected to an inlet of a further heat exchanger located in a large tank of water which forms a heat sink. The further heat exchanger's outlet is connected to the heat exchanger's inlet forming a closed loop. The further heat exchanger is located at a higher elevation than the heat exchanger whereby a natural convection flow can occur in the decay heat removal path. Normally, the vapor/liquid interface in the loop is at a higher elevation than the heat sink which prevents any significant natural convection flow until boiling of the second liquid coolant occurs in the heat exchanger. If the steam generator is lost as a heat sink, this causes boiling of the secondary coolant to occur in the heat exchanger starting a natural convection flow in the decay heat removal loop. This natural convection starts automatically without the need of any valves being opened or any other type of intervention.