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 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.

The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction.

The technical result of the claimed invention consists in increasing the reliability of the corium localizing and cooling system of the nuclear reactor, increase of heat removal efficiency from corium of the nuclear reactor.

The technical result is achieved by using upper heat insulation in the corium localizing and cooling system of the nuclear reactor, installed in the area between the reactor pressure vessel and cantilever truss, and lower thermal protection installed inside the reactor pressure vessel on the filler upper cassette.

According to an embodiment, a nuclear plant has: an outer well; an in-Containment Atmosphere Dilution System to inject a gas that has a low concentration of oxygen in the outer well into a containment vessel; an accumulator containing pressurized oxygen therein; and a passive containment cooling system including: a scrubbing pool arranged in the outer well; a cooling water pool installed above a dry well and the outer well; a heat exchanger partly submerged in a cooling water; a wet well gas supply pipe that is connected to an inlet plenum of the heat exchanger at one end and connected to a wet well gas phase at the other end; and a gas vent pipe that is connected to an outlet plenum of the heat exchanger at one end and is submerged in the scrubbing pool at the other end.

According to an embodiment, a nuclear plant has: an outer well; an in-Containment Atmosphere Dilution System to inject a gas that has a low concentration of oxygen in the outer well into a containment vessel; an accumulator containing pressurized oxygen therein; and a passive containment cooling system including: a scrubbing pool arranged in the outer well; a cooling water pool installed above a dry well and the outer well; a heat exchanger partly submerged in a cooling water; a wet well gas supply pipe that is connected to an inlet plenum of the heat exchanger at one end and connected to a wet well gas phase at the other end; and a gas vent pipe that is connected to an outlet plenum of the heat exchanger at one end and is submerged in the scrubbing pool at the other end.

Disclosed herein is a reactor including a reactor vessel and a containment vessel configured to surround the reactor vessel. The containment vessel includes a thermal radiation shield disposed on an inner wall, and a gap between the reactor vessel and the containment vessel is in an atmospheric pressure and air atmosphere state.

Disclosed herein is a reactor including a reactor vessel and a containment vessel configured to surround the reactor vessel. The containment vessel includes a thermal radiation shield disposed on an inner wall, and a gap between the reactor vessel and the containment vessel is in an atmospheric pressure and air atmosphere state.

An anti-seismic apparatus for control element drive mechanisms of a nuclear reactor includes: an anti-seismic support plate including a plurality of insertion holes in which the control element drive mechanisms are respectively inserted; and bushings inserted between outer surfaces of the control element drive mechanisms and inner surfaces of the insertion holes. The support plate includes an upper support plate comprising a plurality of first insertion holes, a lower support plate comprising a plurality of second insertion holes at positions corresponding to the first insertion holes, and a connection part connecting the upper support plate and the lower support plate. The connection part includes a support beam vertically extending from an end portion of the lower support plate, an inner flange extending inward from an upper end portion of the support beam, and an outer flange extending outward from the upper end portion of the support beam.

An anti-seismic apparatus for control element drive mechanisms of a nuclear reactor includes: an anti-seismic support plate including a plurality of insertion holes in which the control element drive mechanisms are respectively inserted; and bushings inserted between outer surfaces of the control element drive mechanisms and inner surfaces of the insertion holes. The support plate includes an upper support plate comprising a plurality of first insertion holes, a lower support plate comprising a plurality of second insertion holes at positions corresponding to the first insertion holes, and a connection part connecting the upper support plate and the lower support plate. The connection part includes a support beam vertically extending from an end portion of the lower support plate, an inner flange extending inward from an upper end portion of the support beam, and an outer flange extending outward from the upper end portion of the support beam.

A nuclear reactor cooled by liquid metal incorporating a passive system for evacuation of the decay heat with a phase change material thermal reservoir and a removable thermally-insulating layer around the phase change material reservoir. A nuclear reactor incorporates an integral system that guarantees: totally passive evacuation of decay heat from the initial moment of the accident; evacuation of power via the primary containment vessel; the presence of a final cold source with a reservoir incorporating an integral exchanger divided into a plurality of parallel tubes between which a phase change material is inserted, the reservoir being surrounded by a thermally-insulating layer that can be detached in a passive manner in the event of reaching a predetermined threshold temperature.