A liquid metal cooled molten salt reactor having a liquid metal vessel connected to a gas chamber that is connected to a molten salt chamber that is connected with a hot liquid metal vessel. A fuel salt that is withdrawn from the fuel salt tank through a feeding tube into the molten salt chamber from which the fuel salt is withdrawn into a salt separator. A purging gas is inserted into the gas chamber and withdrawn. A liquid metal coolant is dispensed from the liquid metal vessel through a plurality of dispensing nozzles into the molten salt chamber. The liquid metal coolant flows through the molten salt into a hot liquid metal vessel and then through a liquid metal filter into a liquid metal pump. The liquid metal coolant flows through a thermal exchanger subsequently returning to the liquid metal vessel.

A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.

A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.

A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

Provided is a reactor secondary side passive residual heat removal system, comprising: a containment vessel; a steam generator provided with a steam outlet and a water supply inlet; a water tank, the water tank being internally provided with a heat exchanger, the heat exchanger having a heat exchanger inlet and a heat exchanger outlet; and a steam driven pump provided with a steam port, a water inlet and a water outlet, wherein the steam generator, the water tank and the steam driven pump are arranged in the containment vessel, the heat exchanger inlet is in communication with the steam outlet of the steam generator by means of a first pipeline, the heat exchanger outlet is in communication with the water inlet of the steam driven pump by means of a second pipeline, the water outlet of the steam driven pump is in communication with the water supply inlet of the steam generator by means of a third pipeline, and the steam port of the steam driven pump is in communication with the first pipeline by means of a fourth pipeline. The present invention does not rely on an external driving force, thereby greatly reducing the failure probability of the system and improving the safety of the system.

Provided is a reactor secondary side passive residual heat removal system, comprising: a containment vessel; a steam generator provided with a steam outlet and a water supply inlet; a water tank, the water tank being internally provided with a heat exchanger, the heat exchanger having a heat exchanger inlet and a heat exchanger outlet; and a steam driven pump provided with a steam port, a water inlet and a water outlet, wherein the steam generator, the water tank and the steam driven pump are arranged in the containment vessel, the heat exchanger inlet is in communication with the steam outlet of the steam generator by means of a first pipeline, the heat exchanger outlet is in communication with the water inlet of the steam driven pump by means of a second pipeline, the water outlet of the steam driven pump is in communication with the water supply inlet of the steam generator by means of a third pipeline, and the steam port of the steam driven pump is in communication with the first pipeline by means of a fourth pipeline. The present invention does not rely on an external driving force, thereby greatly reducing the failure probability of the system and improving the safety of the system.

A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.

A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.

An ERVC for floating nuclear power plants includes a containment, a reactor vessel, a liquid gallium collection tank, a heat pipe, a cooling cabin and a gallium storage tank. The containment is arranged in a sea environment, and the containment is provided with a containing cavity; the reactor vessel and the liquid gallium collection tank are arranged up and down and located in the containing cavity. An end of the heat pipe is inserted into the liquid gallium collection tank, and another end thereof is arranged outside the liquid gallium collection tank; the gallium storage tank is located in the containing cavity; the gallium storage tank is connected to the liquid gallium collection tank through a liquid gallium release valve; and the cooling cabin is located under the containment and under a sea level of the sea environment.