The invention relates to energy, in particular for the system of separation and superheating of steam for nuclear power plant turbines. The invention is aimed at solving the problem of reducing the mass and dimension parameters while maintaining the efficiency of heat exchange.

The task in the claimed invention is solved by the fact that both tube banks of the first and second superheating stages are rotated vertically at the same height in such a way that they form between them and the inside of the housing two segmental inlet headers, a wedged outlet header with an angle of turn from 10 to 90, and the steam outlet nozzle is located in a vertical case opposite the wedged outlet header. The actual reduction in mass and dimension parameters is 18-25%, which allows using this solution in compact systems for steam separation and superheating.

The invention relates to energy, in particular for the system of separation and superheating of steam for nuclear power plant turbines. The invention is aimed at solving the problem of reducing the mass and dimension parameters while maintaining the efficiency of heat exchange.

The task in the claimed invention is solved by the fact that both tube banks of the first and second superheating stages are rotated vertically at the same height in such a way that they form between them and the inside of the housing two segmental inlet headers, a wedged outlet header with an angle of turn from 10 to 90, and the steam outlet nozzle is located in a vertical case opposite the wedged outlet header. The actual reduction in mass and dimension parameters is 18-25%, which allows using this solution in compact systems for steam separation and superheating.

A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant.

A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant.