An external reactor vessel cooling and electric power generation system according to the present invention includes an external reactor vessel cooling section formed to enclose at least part of a reactor vessel with small-scale facilities so as to cool heat discharged from the reactor vessel, a power production section including a small turbine and a small generator to generate electric energy using a fluid that receives heat from the external reactor vessel cooling section, a condensation heat exchange section 140 to perform a heat exchange of the fluid discharged after operating the small turbine, and condense the fluid to generate condensed water, and a condensed water storage section to collect therein the condensed water generated in the condensation heat exchange section, wherein the fluid is phase-changed into gas by the heat received from the reactor vessel. The external reactor vessel cooling and electric power generation system according to the present invention can continuously operate even during an accident as well as during a normal operation to cool the reactor vessel and produce emergency power, thereby enhancing system reliability. The external reactor vessel cooling and electric power generation system according to the present invention can easily apply safety class or seismic design using small-scale facilities, and its reliability can be improved owing to applying the safety class or seismic design.

An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.

An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.

The patent discloses method and control system for gas injection into the coolant of a nuclear reactor plant. The method includes the following steps: gas to be injected into the coolant is supplied from the gas system to the above-coolant space; gas is injected into the gas system from the above-coolant space. Technical result: prevention of reuse of contaminated gas.

The patent discloses method and control system for gas injection into the coolant of a nuclear reactor plant. The method includes the following steps: gas to be injected into the coolant is supplied from the gas system to the above-coolant space; gas is injected into the gas system from the above-coolant space. Technical result: prevention of reuse of contaminated gas.

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 molten salt reactor system includes a fuel salt system configured to circulate a molten salt through a reactor vessel. The molten salt reactor system further includes an inert gas system fluidically coupled with the fuel salt system and configured to maintain a pressurized volume fluidically between the molten salt and a drain tank by circulating an inert gas along a first inert flow path. The molten salt reactor system further includes an equalization system configured to equalize pressure between all head spaces of the molten salt reactor system including the reactor vessel and the drain tank in response to a shutdown event. The inert gas system is configured to cease maintenance of the pressurized volume in response to the shutdown event.

A nuclear reactor plant including a reactor; a coolant in the reactor; a gas system connected to the reactor and adapted to provide a gas supply to and gas removal from a space above the coolant; and a device for injection of gas into the coolant. The device is installed partially in the coolant and partially in the space above the coolant, and is adapted to supply gas from the space above the coolant to the coolant. The gas system and device are configured to carry out steps including: supplying gas to be injected into the coolant from the gas system to the space above the coolant space; injecting gas into the coolant by maintaining the gas pressure higher than coolant pressure in the device; and injecting gas into the gas system from the space above the coolant.

A nuclear reactor plant including a reactor; a coolant in the reactor; a gas system connected to the reactor and adapted to provide a gas supply to and gas removal from a space above the coolant; and a device for injection of gas into the coolant. The device is installed partially in the coolant and partially in the space above the coolant, and is adapted to supply gas from the space above the coolant to the coolant. The gas system and device are configured to carry out steps including: supplying gas to be injected into the coolant from the gas system to the space above the coolant space; injecting gas into the coolant by maintaining the gas pressure higher than coolant pressure in the device; and injecting gas into the gas system from the space above the coolant.

A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.