Patent classifications
G21D5/12
External reactor vessel cooling and electric power generation system
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.
External reactor vessel cooling and electric power generation system
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.
Nuclear-powered turbine engine
A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.
Nuclear-powered turbine engine
A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.
NUCLEAR-POWERED TURBINE ENGINE
A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.
NUCLEAR-POWERED TURBINE ENGINE
A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.
SYSTEMS AND METHODS FOR STEAM REHEAT IN POWER PLANTS
Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.
SYSTEMS AND METHODS FOR STEAM REHEAT IN POWER PLANTS
Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.
Storage rack for nuclear fuel assemblies
A racking device is provided for storing and/or transporting nuclear fuel assemblies. The racking device includes first stages (Ei1, Ei+1) for neutron absorption and thermal conductivity, as well as second stages (E2i) for mechanical strength arranged so as to alternate with the first stages. Each first stage (Ei1, Ei+1) includes first and second assemblies having interlacing notches (6a, 6b) made of aluminium alloy including boron. Each second stage (Ei) includes first and second structures (7a, 7b) stacked in a stacking direction (8) and each is made of one or more materials which are free of neutron-absorbing elements. The first and second structures (7a, 7b) are free of notches on their opposite edges in the stacking direction (8).
Storage rack for nuclear fuel assemblies
A racking device is provided for storing and/or transporting nuclear fuel assemblies. The racking device includes first stages (Ei1, Ei+1) for neutron absorption and thermal conductivity, as well as second stages (E2i) for mechanical strength arranged so as to alternate with the first stages. Each first stage (Ei1, Ei+1) includes first and second assemblies having interlacing notches (6a, 6b) made of aluminium alloy including boron. Each second stage (Ei) includes first and second structures (7a, 7b) stacked in a stacking direction (8) and each is made of one or more materials which are free of neutron-absorbing elements. The first and second structures (7a, 7b) are free of notches on their opposite edges in the stacking direction (8).