A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.

A canned rotodynamic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor. The stator windings are formed by one or more electrically conductive solid bars (12).

A compact pressurized water nuclear reactor having connected to the reactor pressure vessel a plurality of pressure vessels connected by nozzles, and connected by curved horizontal pressure vessel heads by having their central axis horizontal, with reduced stress and simple single connection between the respective nozzle of the reactor pressure vessel with the respective nozzle of each curved horizontal pressure vessel heads, all with the same internal and external design pressure.

A compact pressurized water nuclear reactor having connected to the reactor pressure vessel a plurality of pressure vessels connected by nozzles, and connected by curved horizontal pressure vessel heads by having their central axis horizontal, with reduced stress and simple single connection between the respective nozzle of the reactor pressure vessel with the respective nozzle of each curved horizontal pressure vessel heads, all with the same internal and external design pressure.

A device for removing foreign matters in nuclear reactor vessel comprises a suction pipe; a suction opening structure disposed at a lower end of the suction pipe, wherein the suction opening structure has a suction opening thereon; an electric valve disposed at a connection of the suction pipe and the flared pipe; and a filter mesh and a suction pump sequentially located in the suction pipe and above the electric valve; wherein a water inlet of the suction pump is communicated with the suction opening, a water outlet of the suction pump is communicated with the outside space of the suction pipe though a drainage pipe, and the electric valve is controlled by the touch switch. The device has a simple structure and is easy for operation, through which foreign matters can be taken out of the reactor vessel even though their specific location is not known.

A device for removing foreign matters in nuclear reactor vessel comprises a suction pipe; a suction opening structure disposed at a lower end of the suction pipe, wherein the suction opening structure has a suction opening thereon; an electric valve disposed at a connection of the suction pipe and the flared pipe; and a filter mesh and a suction pump sequentially located in the suction pipe and above the electric valve; wherein a water inlet of the suction pump is communicated with the suction opening, a water outlet of the suction pump is communicated with the outside space of the suction pipe though a drainage pipe, and the electric valve is controlled by the touch switch. The device has a simple structure and is easy for operation, through which foreign matters can be taken out of the reactor vessel even though their specific location is not known.

A gas-cooled pressure tube nuclear reactor is described that uses a room temperature and pressure gas as a primary coolant and a liquid moderator as a secondary coolant. The primary coolant, which may be maintained in a supercritical state, is circulated through fuel columns in a pool of the liquid moderator. The primary coolant removes the heat generated by fission from the nuclear fuel. The heated primary coolant is then passed to one or more turbines to generate power. The primary coolant is then repressurized by one or more compressors using some of the generated power from the turbines. Several modified Brayton cycle configurations are described that are uniquely suited to the operating conditions of the gas-cooled pressure tube reactor.

A gas-cooled pressure tube nuclear reactor is described that uses a room temperature and pressure gas as a primary coolant and a liquid moderator as a secondary coolant. The primary coolant, which may be maintained in a supercritical state, is circulated through fuel columns in a pool of the liquid moderator. The primary coolant removes the heat generated by fission from the nuclear fuel. The heated primary coolant is then passed to one or more turbines to generate power. The primary coolant is then repressurized by one or more compressors using some of the generated power from the turbines. Several modified Brayton cycle configurations are described that are uniquely suited to the operating conditions of the gas-cooled pressure tube reactor.

A nuclear power plant comprising a primary coolant circuit, a steam-water circuit separated from the primary coolant circuit and a steam generator connected to the primary coolant circuit and the steam-water circuit to transfer heat from the primary coolant circuit into the steam-water circuit has at least one dosing point in the steam-water circuit to inject a reducing agent into the steam-water circuit, wherein the reducing agent is an organic compound consisting of carbon, hydrogen and oxygen. Furthermore, a method for operating said nuclear power plant and the use of the method for downtime preservation of the secondary side of a steam generator of a nuclear power plant are provided.

A nuclear power plant comprising a primary coolant circuit, a steam-water circuit separated from the primary coolant circuit and a steam generator connected to the primary coolant circuit and the steam-water circuit to transfer heat from the primary coolant circuit into the steam-water circuit has at least one dosing point in the steam-water circuit to inject a reducing agent into the steam-water circuit, wherein the reducing agent is an organic compound consisting of carbon, hydrogen and oxygen. Furthermore, a method for operating said nuclear power plant and the use of the method for downtime preservation of the secondary side of a steam generator of a nuclear power plant are provided.