A steam generator that reduces the thermal and hydraulic unevenness in the steam generator, improves the filling capacity of the steam generator with heat exchange tubes, organizes an economizer portion of the heat exchange surface in the steam generator, and reduces the concentration of corrosive impurities in the weld zone of the primary circuit to the horizontal shell. To solve the task in such steam generator containing the horizontal shell and other component, the heat exchange tubes are located in vertical planes, and the inlet and outlet manifolds of the primary circuit are arranged horizontally. The steam generator can also be equipped with at least two output manifolds of the primary circuit furthers, the feed water dispenser can be located below the heat exchange tubes of the steam generator.

A steam generator that reduces the thermal and hydraulic unevenness in the steam generator, improves the filling capacity of the steam generator with heat exchange tubes, organizes an economizer portion of the heat exchange surface in the steam generator, and reduces the concentration of corrosive impurities in the weld zone of the primary circuit to the horizontal shell. To solve the task in such steam generator containing the horizontal shell and other component, the heat exchange tubes are located in vertical planes, and the inlet and outlet manifolds of the primary circuit are arranged horizontally. The steam generator can also be equipped with at least two output manifolds of the primary circuit furthers, the feed water dispenser can be located below the heat exchange tubes of the steam generator.

A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

The present invention relates to an apparatus for efficiently and economically generating a cooling medium by using high-temperature and high-pressure steam generated in a nuclear power plant, and cooling method therefor. According to one embodiment of the present invention, the cooling medium generating apparatus provided in a containment vessel of a nuclear power generation facility so as to generate the cooling medium can comprise: a nuclear reactor for heating a coolant by using heat included in the heated coolant; a cooling module for generating the cooling medium by using the steam generated in the steam generator; and a cooling medium supplying pipe of which the end portion is connected to the outside of the containment vessel so as to supply the cooling medium, having been generated in the cooling module, to the outside of the containment vessel.

A compact pressurized water nuclear reactor having connected to the reactor pressure vessel a plurality of horizontal pressure vessels, with all the horizontal pressure vessels connected to the reactor pressure vessel by a single connection between the respective nozzle of the reactor pressure vessel with the respective nozzle of each horizontal pressure vessel.

A steam generator includes a lower integrated tubesheet and plenum (ITP) configured to receive feedwater and a first set of heat transfer tubes fluidly coupled to a plurality of stubs protruding from a first side of the lower ITP. A second set of heat transfer tubes fluidly couples to plurality of stubs protruding from a second side of the lower ITP. The first set of heat transfer tubes is coiled in a substantially clock-wise direction, and the second set of heat transfer tubes is coiled in a substantially counter-clockwise direction. The steam generator further includes an upper ITP fluidly coupled to the first and second set of heat transfer tubes, wherein the feedwater entering the lower ITP is converted to steam in the first and second sets of heat transfer tubes. The upper ITP is configured to transport the steam away from the steam generator.

The invention relates to an electrical energy generation facility comprising: a steam generation device (1) that is suitable for producing saturated steam (VI) from a heat source and is arranged in a chamber (10); a set of one or more separators (13) that is/are connected downstream to the steam generation device (1) and is/are suitable for removing most of the water from the steam (VI) generated by the device (1), said set being arranged in the chamber (10); a set of one or more dryers (14) which is connected upstream to the set of separators (13) and is suitable for collecting the water droplets suspended in the steam (V2) that is discharged from the set of separators so as to generate dry steam (V3); a steam turbine (2) comprising at least one body (20) for expanding dry steam (V3), the steam turbine being suitable for producing electricity from the dry steam (V3); a set of exchangers (23, 7) suitable for operating as steam superheaters or for reheating supply water; the set of one or more dryers (14) is arranged outside the chamber (10) of the steam generation device (1), the inlet (14a) of the set of dryers is connected upstream to the set of separators (13), a first outlet (14b) is connected downstream to the inlet of the body (20) of the turbine, and a second outlet (14c) is connected downstream, as a heat source, to the set of exchangers (23, 7).

A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

A waste treatment system 100 for performing a hydrothermal treatment of wastes includes a hydrothermal treatment device 10 for performing the hydrothermal treatment by bringing steam into contact with the wastes, a storage facility 8, 9 for storing a fuel produced from a reactant of the hydrothermal treatment, and a heat recovery steam generator 18 for generating the steam to be supplied to the hydrothermal treatment device 10. The heat recovery steam generator 18 is configured to generate the steam by using a combustion energy generated by combustion of the fuel stored in the storage facility 8, 9.

A waste treatment system 100 for performing a hydrothermal treatment of wastes includes a hydrothermal treatment device 10 for performing the hydrothermal treatment by bringing steam into contact with the wastes, a storage facility 8, 9 for storing a fuel produced from a reactant of the hydrothermal treatment, and a heat recovery steam generator 18 for generating the steam to be supplied to the hydrothermal treatment device 10. The heat recovery steam generator 18 is configured to generate the steam by using a combustion energy generated by combustion of the fuel stored in the storage facility 8, 9.