The invention relates to energy mechanical engineering and can be used in power installations involving a liquid-metal heat carrier. A mass transfer apparatus including a housing and, provided therein, a flow reaction chamber filled with a solid-phase granulated oxidation agent, and an electric heater positioned in the reaction chamber. The housing of the apparatus is equipped with a repository for reserves of the solid-state granulated oxidation agent, said repository being located below the reaction chamber and being made in the form of a cup having a bottom, said cup being connected to the re-action chamber. The technical result consists in extending the operational duration of the mass transfer apparatus.

A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.

A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.

A compact nuclear power generation system includes a reactor (3) comprising a core (2) which uses metal fuel containing either or both of uranium-235/238 and plutonium-239. A reactor vessel (1) houses the core (2). Metal sodium primary coolant (8) is heated by the core (2). A neutron reflector (9) maintains the effective multiplication factor of neutrons emitted from the core (2) at approximately one or more to bring the core into a critical state. The neutron reflector is movable from a lower part towards an upper part of the core. The heated metal sodium is supplied to a main heat exchanger (15) which is located outside the reactor. A secondary coolant of supercritical carbon dioxide, which circulates through the main heat exchanger, is in heat exchange with the heated metal sodium. The heated secondary coolant drives a turbine (20). A power generator (21) can be operated by the driven turbine.

A compact nuclear power generation system includes a reactor (3) comprising a core (2) which uses metal fuel containing either or both of uranium-235/238 and plutonium-239. A reactor vessel (1) houses the core (2). Metal sodium primary coolant (8) is heated by the core (2). A neutron reflector (9) maintains the effective multiplication factor of neutrons emitted from the core (2) at approximately one or more to bring the core into a critical state. The neutron reflector is movable from a lower part towards an upper part of the core. The heated metal sodium is supplied to a main heat exchanger (15) which is located outside the reactor. A secondary coolant of supercritical carbon dioxide, which circulates through the main heat exchanger, is in heat exchange with the heated metal sodium. The heated secondary coolant drives a turbine (20). A power generator (21) can be operated by the driven turbine.

A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel and a nuclear reactor core disposed in a lower vessel section. A hollow cylindrical central riser is disposed concentrically inside the pressure vessel. A downcomer annulus is defined between the central riser and the pressure vessel. A reactor coolant pump (RCP) includes (i) an impeller disposed above the nuclear reactor core and in fluid communication with the downcomer annulus to impel primary coolant downward through the downcomer annulus, (ii) a pump motor disposed outside of the pressure vessel, and (iii) a drive shaft operatively connecting the pump motor with the impeller. The PWR may include an internal steam generator in the downcomer annulus, with the impeller is disposed below the steam generator. The impeller may be disposed in the downcomer annulus. The RCP may further comprise a pump casing that with the impeller defines a centrifugal pump.

A pressurized water nuclear reactor (PWR) includes a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume. A condenser is secured to, and optionally supported by, the upper portion of the pressure vessel. A condenser inlet is in fluid communication with the internal pressurizer volume. A heat sink is in fluid communication with the condenser such that the condenser operates as a passive heat exchanger to condense steam from the internal pressurizer volume into condensate while rejecting heat to the heat sink. A condenser outlet connects with the pressure vessel to return condensate to the pressure vessel. A single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser inlet may provide the fluid communication between the condenser inlet and the internal pressurizer volume.

A pressurized water reactor (PWR) comprises: a nuclear core comprising a fissile material; a cylindrical pressure vessel having a vertically oriented cylinder axis and containing the nuclear core immersed in primary coolant water; and a hollow cylindrical central riser disposed concentrically with and inside the cylindrical pressure vessel. A downcomer annulus is defined between the hollow cylindrical central riser and the cylindrical pressure vessel. The hollow cylindrical central riser has a radially expanding upper orifice that merges into an annular divider plate that separates an upper plenum above the annular divider plate from a lower plenum below the annular divider plate. The upper plenum is in fluid communication with the radially expanding upper orifice and the lower plenum is in fluid communication with the downcomer annulus. A weir may extend away from a bottom wall of the lower plenum into the lower plenum. An emergency core cooling system (ECCS) return line nozzle may be arranged to inject water into the upper plenum. A pump support plate spans the inner diameter of the cylindrical pressure vessel and forms a portion of the pressure boundary of the cylindrical pressure vessel, and reactor coolant pumps (RCPs) are supported by the pump support plate. Alternatively, reactor coolant pumps (RCPs) are supported by an arcuate annular ledge formed in the upper portion of the cylindrical pressure vessel.

A thermal power reactor is provided. The thermal power reactor includes a reactor core arranged to generate thermal energy and a solid state thermal conductor including a graphene based metamaterial. The solid state thermal conductor extends into and is thermally integrated with the reactor core. The solid state thermal conductor is arranged to transfer thermal energy generated by the reactor core away from the reactor core.

A thermal power reactor is provided. The thermal power reactor includes a reactor core arranged to generate thermal energy and a solid state thermal conductor including a graphene based metamaterial. The solid state thermal conductor extends into and is thermally integrated with the reactor core. The solid state thermal conductor is arranged to transfer thermal energy generated by the reactor core away from the reactor core.