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 A fuel salt that is withdrawn from the fuel salt tank through a feeding tube into the molten salt chamber from which the fuel salt is withdrawn into a salt separator. A purging gas is inserted into the gas chamber and withdrawn.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.

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.

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.

A nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, includes a main vessel with a hot leg and a cold leg, the cold leg encompassing the hot leg; a core submerged in the hot leg; at least one heat exchanger; at least one primary fluid circulation pump pressurizing one of the legs; a reactor lid; a gas plenum; and an inner lid provided beneath the reactor lid to cover the pressurized leg.

A nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, includes a main vessel with a hot leg and a cold leg, the cold leg encompassing the hot leg; a core submerged in the hot leg; at least one heat exchanger; at least one primary fluid circulation pump pressurizing one of the legs; a reactor lid; a gas plenum; and an inner lid provided beneath the reactor lid to cover the pressurized leg.

Passive safety systems cool reactors using surrounding ground as a heat sink. A coolant flow channel may loop around the reactor and then pass outside, potentially through a containment building, into surrounding ground. No active components need be used in example embodiment safety systems, which may be driven entirely by gravity-based natural circulation. The coolant loop may be air-tight and seismically-hardened and filled with any coolant such as water, air, nitrogen, a noble gas, a refrigerant, etc. The ground may include a soil of grey limestone, soft grey fine sandy clay, grey slightly silty sandy gravel, etc. or any other fill with desired heat-transfer characteristics. Coolant fins and/or jackets with secondary coolants may be used on the coolant loop. The coolant loop may be buried at any constant or variable depth, and the reactor and containment may also be buried in the ground.

The invention concerns a liquid metal-cooled fast-neutron nuclear reactor (1), comprising a system (2) for removing at least part of both the nominal power and the residual power of the reactor, which ensures, at the same time: removal of the residual power in a totally passive manner from the initial instant of the accident; removal of the heat through the primary vessel; implementation of a final cold source (container with PCM) other than the sodium/air or NaK/air heat exchangers used in the prior art.

The invention concerns a liquid metal-cooled fast-neutron nuclear reactor (1), comprising a system (2) for removing at least part of both the nominal power and the residual power of the reactor, which ensures, at the same time: removal of the residual power in a totally passive manner from the initial instant of the accident; removal of the heat through the primary vessel; implementation of a final cold source (container with PCM) other than the sodium/air or NaK/air heat exchangers used in the prior art.

A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

A liquid metal-cooled nuclear reactor includes, within a reactor pressure vessel having a reactor core, a multistage annular linear induction pump (ALIP) configured to circulate liquid metal coolant through the reactor core. The multistage ALIP includes multiple sets of induction coils that at least partially define separate, respective stages of the multistage ALIP. The multiple sets of induction coils are configured to be electrically connected to separate, respective polyphase power supplies, such that the stages of the multistage ALIP are configured to be controlled independently of each other to adjustably control a flow of liquid metal coolant through the reactor core based on independent control of the multiple polyphase power supplies.