Patent classifications
F22B37/268
STEAM BOILER LIQUID SEPARATOR AND METHOD FOR THE PRODUCTION THEREOF
A steam boiler liquid separator having a plurality of liquid separator segments connected together to form a shaft disposed inside a pipe section, with swirl vanes disposed around the shaft. The liquid separator segments each include a shaft segment connected to a pipe segment by a swirl vane such that the shaft segment is disposed radially inward from the pipe segment.
Multiple-path flow restrictor nozzle
A flow restrictor nozzle for a pressurized vessel of a nuclear reactor may comprise a nozzle body including an inlet face and an outlet face. The nozzle body may define a plurality of internal flow paths extending from the inlet face to the outlet face. Each of the plurality of internal flow paths may include a convergent section, a throat section, and a divergent section.
Steam turbine plant
A steam turbine plant includes a high-medium pressure turbine having a high-pressure turbine section provided at one end portion in an axial direction and a medium-pressure turbine section provided at the other end portion; a low-pressure turbine disposed coaxially with the high-medium pressure turbine; a condenser configured to cool steam used in the low-pressure turbine to condense the steam into condensate; and a feed-water heater configured to heat the condensate with steam discharged from the high-pressure turbine section. The plant also includes a low-pressure moisture separating and heating device configured to remove moisture of steam discharged from the medium-pressure turbine section, and to heat the steam with a part of steam to be sent to an inlet portion of the high-pressure turbine section and a part of steam to be sent to an inlet portion of the medium-pressure turbine section from an outlet portion of the high-pressure turbine section.
COOLANT RECIRCULATION SYSTEM OF NUCLEAR POWER PLANT
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.
Electricity generation facility comprising a device for producing steam of reduced height, application to PWR and BWR reactors
The invention relates to an electrical energy generation facility comprising: a steam generation device (1) that is suitable for producing saturated steam (VI) from a heat source and is arranged in a chamber (10); a set of one or more separators (13) that is/are connected downstream to the steam generation device (1) and is/are suitable for removing most of the water from the steam (VI) generated by the device (1), said set being arranged in the chamber (10); a set of one or more dryers (14) which is connected upstream to the set of separators (13) and is suitable for collecting the water droplets suspended in the steam (V2) that is discharged from the set of separators so as to generate dry steam (V3); a steam turbine (2) comprising at least one body (20) for expanding dry steam (V3), the steam turbine being suitable for producing electricity from the dry steam (V3); a set of exchangers (23, 7) suitable for operating as steam superheaters or for reheating supply water; the set of one or more dryers (14) is arranged outside the chamber (10) of the steam generation device (1), the inlet (14a) of the set of dryers is connected upstream to the set of separators (13), a first outlet (14b) is connected downstream to the inlet of the body (20) of the turbine, and a second outlet (14c) is connected downstream, as a heat source, to the set of exchangers (23, 7).
MULTIPLE-PATH FLOW RESTRICTOR NOZZLE
A flow restrictor nozzle for a pressurized vessel of a nuclear reactor may comprise a nozzle body including an inlet face and an outlet face. The nozzle body may define a plurality of internal flow paths extending from the inlet face to the outlet face. Each of the plurality of internal flow paths may include a convergent section, a throat section, and a divergent section.
NUCLEAR POWER PLANTS
A nuclear power plant, having a reactor pressure vessel; a steam generator arranged to generate steam utilising thermal energy generated within the reactor pressure vessel; and a fluid circuit for transferring thermal energy from the reactor pressure vessel to the steam generator. The plant also has a coolant reservoir for storing coolant for supply to the steam generator under gravity in emergency conditions. The steam generator has a steam drying zone comprising one or more steam separators configured to dry steam; and the steam generator and coolant reservoir are configured such that when coolant is supplied from the coolant reservoir to the steam generator in emergency conditions the coolant stays below a threshold level defined by the steam drying zone.
STEAM TURBINE PLANT
A steam turbine plant includes a high-medium pressure turbine having a high-pressure turbine section provided at one end portion in an axial direction and a medium-pressure turbine section provided at the other end portion; a low-pressure turbine disposed coaxially with the high-medium pressure turbine; a condenser configured to cool steam used in the low-pressure turbine to condense the steam into condensate; and a feed-water heater configured to heat the condensate with steam discharged from the high-pressure turbine section. The plant also includes a low-pressure moisture separating and heating device configured to remove moisture of steam discharged from the medium-pressure turbine section, and to heat the steam with a part of steam to be sent to an inlet portion of the high-pressure turbine section and a part of steam to be sent to an inlet portion of the medium-pressure turbine section from an outlet portion of the high-pressure turbine section.
Steam separation system and nuclear boiling water reactor including the same
In one embodiment, the steam separation system includes a plurality of steam separators configured to separate liquid from a gas-liquid two-phase flow stream; and a steam dryer system disposed above the steam separators. The steam dryer system includes a plurality of steam dryer bank assemblies and at least one moisture trap. Each of the steam dryer bank assemblies is configured to separate liquid of the gas-liquid two-phase flow stream exiting the steam separators. The moisture trap is disposed next to one of the steam dryer bank assemblies and is configured to remove liquid from the gas-liquid two-phase flow stream.
Swirler, steam separator including the swirler, and nuclear boiling water reactor including the same
In one embodiment, the steam separator includes a standpipe configured to receive a gas-liquid two-phase flow stream, and a first swirler configured to receive the gas-liquid two-phase flow stream from the standpipe. The first swirler is configured to separate the gas-liquid two-phase flow stream. The first swirler includes a direct flow portion and an indirect flow portion. The direct flow portion has a direct flow channel for permitting direct flow of the gas-liquid two-phase flow stream through the first swirler, and the indirect flow portion has at least one indirect flow channel defined by at least one vane in the first swirler for providing an indirect flow of the gas-liquid two-phase flow stream through the first swirler.