The invention provides a
system and method for carrying heat after a power failure accident of a whole
nuclear power plant. The
system comprises a pressure container, a
voltage stabilizer, a steam generator and a PRS
heat exchanger. Wherein the pressure container and the steam generator form
water circulation, a first emergency water
injection pump is arranged on a path from the steam generator to the pressure container, a generator is arranged on one side of the water
injection pump, and the generator is electrically connected with the first emergency water
injection pump; a path from the pressure container to the steam generator is communicated with a pressure stabilizer; the air inlet end of the PRS
heat exchanger communicates with the top of the steam generator, the air outlet end of the PRS
heat exchanger communicates with the middle of the steam generator, and a second emergency water injection pump is arranged on the communicating path of the air outlet end of the PRS heat exchanger and the middle of the steam generator. A
safety valve group and a quick pressure
relief valve group are arranged at the top of the pressure stabilizer; and an
atmosphere discharge valve is arranged at the top of the steam generator. The investment of the
nuclear power plant is reduced on the premise that the safety of the
nuclear power plant is not reduced, and a theoretical foundation is laid for subsequent practical
engineering application.