The present disclosure relates to an L-shaped header of a steam generator including a spiral heat transfer tube, and a coupling structure between the L-shaped header and the heat transfer tube, wherein an upper end and a lower end of a heat transfer tube assembly configured with a plurality of heat transfer tubes are vertically formed, and the upper and lower ends of the heat transfer tube assembly are vertically coupled to a bottom side or a top side of the header. Therefore, the heat transfer tubes constituting the same concentric circle may use the heat transfer tubes formed with the same shape, thereby improving the manufacturability of parts and reducing the manufacturing cost.

A remotely operated vehicle (ROV) for inspecting a core shroud having an outer surface may include: a body configured to be operatively connected to a tether; and/or a sensor, configured to be operatively connected to the body, and configured to provide inspection information of the shroud. The tether may be configured to provide vertical position information for the ROV relative to the outer surface. A system for inspecting a core shroud may include: a trolley; an arm; the tether; and/or the ROV. The arm may be configured to be operatively connected to the trolley. The ROV may be configured to be operatively connected to the arm via the tether. A method for inspecting a core shroud may include: installing a system for inspecting the shroud on the shroud; driving the system horizontally around the shroud; and/or using a sensor of the system to inspect the shroud.

An apparatus for cooling a substructure of a steam generator in a nuclear reactor is provided. The apparatus includes a plurality of stud bolts (110) fastening a skirt of the steam generator to a sliding base. Each stud bolt is provided at the center thereof with an axial through hole (112), a flange of the skirt is provided on one side thereof with a vent passage (122), and each stud bolt is provided with at least one vent hole (114) communicating with the axial through hole (112), thereby forming an air circulation/cooling path between the vent passage (122) and the axial through hole (112) via the vent hole (114).

A coolant recirculation system of a nuclear power plant is provided that may include: a reactor vessel configured to accommodate a reactor core and a reactor coolant therein; a steam generator configured to transfer a gas, converted from a liquid phase to a gaseous phase by exchanging heat with the reactor coolant, to a turbine system; a pressurizer configured to control pressure of the reactor coolant in the reactor vessel; a primary system pressure reducing valve located above the pressurizer and configured to open at a predetermined pressure to discharge the reactor coolant into a containment building for rapid depressurization; and a moisture separator connected to the primary system pressure reducing valve to separate moisture. The moisture separator may separate the reactor coolant into a gaseous phase and a liquid phase. Then, the liquid phase reactor coolant may be returned to the reactor vessel to be recirculated.

The group of inventions refers to heat exchange machinery. The device includes a tank with an outlet fitting and a steam source, a deaerator column with a cover and water inlet and vapor blowdown fittings located on the same, containing lower and upper deaeration sections. Each section includes pressure and distribution trays forming a jet chamber in the space between them, and random element packing. Deaeration sections are separated by a hydraulic seal formed by the edge of the upper section pressure tray and the projection connected to the deaerator column cover. The water inlet and vapor blowdown fittings are located inside the hydraulic seal projection with openings in it. The lower edges of the openings are located higher than the upper edge of the hydraulic seal by a value exceeding the sum of overflow height of the coolant over the edge and hydraulic resistance of the hydraulic seal channel. The total cross section of the openings is determined by equality of steam pressure in the blowdown fitting and in the space inside the hydraulic seal projection. This increases the operation reliability.

Various exemplary embodiments of a power conversion system for converting thermal energy from a heat source to electricity are disclosed. In one exemplary embodiment, the power conversion system may include a substantially sealed chamber having an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The sealed chamber may also include an outer shroud substantially surrounding the inner shroud, such that the working fluid exiting the outlet of the inner shroud returns to the inlet of the inner shroud in a closed-loop via a return passageway formed between an external surface of the inner shroud and an internal surface of the outer shroud. The power conversion system may further include a source heat exchanger disposed in the internal passageway of the inner shroud, the source heat exchanger being configured to at least partially receive a heat transmitting element.

A vibration-inhibiting bar is provided that is interposed between bends of the tubes of two adjacent banks of tubes of a U tube bundle of a steam generator and includes at least one internal element, referred to as a damping element, designed to mechanically damp the vibrations of the tubes; and at least one external element, referred to as percussion element, in contact with the damping element, the percussion element being designed to be in contact with the bends of the tubes of the bundle.

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 power plant with a steam dump device and condenser for the nuclear power plant.

An apparatus for cooling a substructure of a steam generator in a nuclear reactor is provided. The apparatus includes a plurality of stud bolts (110) fastening a skirt of the steam generator to a sliding base. Each stud bolt is provided at the center thereof with an axial through hole (112), a flange of the skirt is provided on one side thereof with a vent passage (122), and each stud bolt is provided with at least one vent hole (114) communicating with the axial through hole (112), thereby forming an air circulation/cooling path between the vent passage (122) and the axial through hole (112) via the vent hole (114).