A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.

A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.

A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.

A condensation system for recuperating the energy discharge of a nuclear power plant comprises a nuclear power unit, an air intake means, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The air intake structure is connected to a compressor, which is connected to the condenser, which is connected to the turboexpander, which is supplied with the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the air intake structure is accommodated in the discharge water channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

A condensation system for recuperating the energy discharge of a nuclear power plant comprises a nuclear power unit, an air intake means, a compressor, a condenser, a water chamber equipped with a sprinkler, an electrical current generator, a pure water pump station, a cooling water pump station, a secondary condensate pool and a turboexpander. The air intake structure is connected to a compressor, which is connected to the condenser, which is connected to the turboexpander, which is supplied with the electric current generator and is connected to the water chamber, which is connected to the secondary condensate pool, which is connected to the pure water pump station, the condenser being connected to the cooling water pump station, wherein the air intake structure is accommodated in the discharge water channel, which is connected to the nuclear power unit and is equipped with a sealing cover.

A device for removing foreign objects from nuclear reactor vessel includes a suction pipe; a suction opening structure disposed at a lower end of the suction pipe, an electric valve disposed at a connection of the suction pipe and the suction opening structure, a filter mesh and a suction pump sequentially located in the suction pipe and above the electric valve. The suction opening structure has a suction opening thereon, a water inlet of the suction pump is communicated with the suction opening, and a water outlet of the suction pump is communicated with the outside space of the suction pipe though a drainage pipe. The device further includes a touch switch disposed on the filter mesh which is in operative connection with the electric valve. A foreign object impact force to the filter mesh triggers the touch switch to close which causes the electric valve to close.

A device for removing foreign objects from nuclear reactor vessel includes a suction pipe; a suction opening structure disposed at a lower end of the suction pipe, an electric valve disposed at a connection of the suction pipe and the suction opening structure, a filter mesh and a suction pump sequentially located in the suction pipe and above the electric valve. The suction opening structure has a suction opening thereon, a water inlet of the suction pump is communicated with the suction opening, and a water outlet of the suction pump is communicated with the outside space of the suction pipe though a drainage pipe. The device further includes a touch switch disposed on the filter mesh which is in operative connection with the electric valve. A foreign object impact force to the filter mesh triggers the touch switch to close which causes the electric valve to close.

A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.