According to an embodiment, a core catcher has: a main body including: a distributor arranged on a part of a base mat in the lower dry well, a basin arranged on the distributor, cooling channels arranged on a lower surface of the basin connected to the distributor and extending in radial directions, and a riser connected to the cooling channels and extending upward; a lid connected to an upper end of the riser and covering the main body; a cooling water injection pipe open, at one end, to the suppression pool, connected at another end to the distributor; and chimney pipes connected, at one end, to the riser, another end being located above the upper end of the riser and submerged and open in the pool water.

The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, including methods and systems for cooling and cooling control of the reactors molten core. The invention increases safety of NPP and cooling efficiency of the molten core of a reactor. The invention increases the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapor explosions. The invention changes the principle of cooling the reactor molten core, in that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.

Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.

Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.

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 a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor.

The technical result is achieved through the use of the membrane and thermal shield installed in the area between the multilayer casing and the cantilever truss in the corium localizing and cooling system of a nuclear reactor.

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 a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor.

The technical result is achieved through the use of the membrane and thermal shield installed in the area between the multilayer casing and the cantilever truss in the corium localizing and cooling system of a nuclear reactor.

Systems for ensuring safety of nuclear power plants (NPPs). The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The corium localizing and cooling system comprise thermal protection suspended to the cantilever truss, the membrane installed between the cantilever truss and the vessel, and the bandage plates installed on the external and internal side of the membrane. The systems prevent destruction of the corium localizing and cooling system within the junction area between the vessel for the corium receipt and distribution and the cantilever truss under the conditions on non-axisymmetric corium escape from the reactor pressure vessel and falling of the reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water, and consequently to prevent any ingress of water intended for external cooling of the vessel into the vessel.

Systems for ensuring safety of nuclear power plants (NPPs). The systems enhance reliability of the corium localizing and cooling system of a nuclear reactor. The corium localizing and cooling system comprise thermal protection suspended to the cantilever truss, the membrane installed between the cantilever truss and the vessel, and the bandage plates installed on the external and internal side of the membrane. The systems prevent destruction of the corium localizing and cooling system within the junction area between the vessel for the corium receipt and distribution and the cantilever truss under the conditions on non-axisymmetric corium escape from the reactor pressure vessel and falling of the reactor pressure vessel head fragments into the vessel at the initial stage of the corium cooling with water, and consequently to prevent any ingress of water intended for external cooling of the vessel into the vessel.

A device for confining nuclear reactor core melt comprising a melt trap and provided with a multilayer vessel containment, a filler, an upper support, and a bottom support comprising a horizontal embedded plate mounted in the concrete of a reactor pit. The plate comprises radial supports, the melt trap comprising radial supports, based on the radial support of the plate. The plate radial supports and the melt trap radial supports are connected with fasteners having holes in the form of hyperbolic surfaces. The radial supports and the clamps have oval holes. The upper support comprises turnbuckles, mounted in pairs on the upper part of the melt trap body so that the longitudinal axis of each radial support of the melt trap bottom support passes in projection at an equispaced distance from the fitting location of the paired turnbuckles and connecting the melt trap body with the reactor pit vertical wall.

A device for confining nuclear reactor core melt comprising a melt trap and provided with a multilayer vessel containment, a filler, an upper support, and a bottom support comprising a horizontal embedded plate mounted in the concrete of a reactor pit. The plate comprises radial supports, the melt trap comprising radial supports, based on the radial support of the plate. The plate radial supports and the melt trap radial supports are connected with fasteners having holes in the form of hyperbolic surfaces. The radial supports and the clamps have oval holes. The upper support comprises turnbuckles, mounted in pairs on the upper part of the melt trap body so that the longitudinal axis of each radial support of the melt trap bottom support passes in projection at an equispaced distance from the fitting location of the paired turnbuckles and connecting the melt trap body with the reactor pit vertical wall.