Patent classifications
G21D1/04
Arrangement and method for providing an emergency supply to a nuclear installation
A method of providing an emergency supply of services to a nuclear power plant having a cooling water cycle, the method including: situating a container at a remote location from the power plant, wherein the container has permanently integrated therein: a motor comprising a first shaft and a second shaft; a generator driven by the first shaft; a pump driven by the second shaft; a fuel tank connected to the motor, and supplying fuel to the motor; and a transformer connected to the generator; connecting the pump to the cooling water cycle of the nuclear power plant; using the pump to pump water from an external water feed into the cooling water cycle of the nuclear power plant.
Arrangement and method for providing an emergency supply to a nuclear installation
A method of providing an emergency supply of services to a nuclear power plant having a cooling water cycle, the method including: situating a container at a remote location from the power plant, wherein the container has permanently integrated therein: a motor comprising a first shaft and a second shaft; a generator driven by the first shaft; a pump driven by the second shaft; a fuel tank connected to the motor, and supplying fuel to the motor; and a transformer connected to the generator; connecting the pump to the cooling water cycle of the nuclear power plant; using the pump to pump water from an external water feed into the cooling water cycle of the nuclear power plant.
Nuclear power plant having a protective superstructure
A nuclear power plant having a protective superstructure including a first end region configured to cover a nuclear reactor in a containment structure, a second end region opposite the first end region and configured to cover a cooling water pump house, and a central region between the first and second end regions and configured to cover a turbine hall. The superstructure has an oval-shaped plan profile, the oval having a greater degree of curvature at the first end region than at the second end region.
Nuclear power plant having a protective superstructure
A nuclear power plant having a protective superstructure including a first end region configured to cover a nuclear reactor in a containment structure, a second end region opposite the first end region and configured to cover a cooling water pump house, and a central region between the first and second end regions and configured to cover a turbine hall. The superstructure has an oval-shaped plan profile, the oval having a greater degree of curvature at the first end region than at the second end region.
COOLANT CLEANUP SYSTEMS WITH DIRECT MIXING AND METHODS OF USING THE SAME
Cleanup systems include plural coolant inputs that are physically combined to create a single flow at a desired filtering temperature. Filter(s) are used to clean the coolant, and coolant flowing therethrough will damage the filter or not be adequately filtered if having temperature in excess of an operating temperature of the filter. The inputs have different temperatures, and mixing them creates a combined flow at a desired temperature. The amount of each flow is selected based on its individual temperature to achieve this desired temperature. The combined flow is then conditioned with the filter at an operable temperature and returned to the coolant origin for the inputs. No heat exchangers or heat loss to outside heat sinks are required. Cleanup systems may be used with any coolant loop, including Rankine-cycle electricity generation systems like nuclear power plants, combustion boilers, and steam generators, and heat transfer systems.
METHOD AND APPARATUS FOR FILTERING FLUID IN NUCLEAR POWER GENERATION
A filtering apparatus for a fluid intake of a nuclear power generation facility comprise primary and secondary frames. The primary frame defines an enclosed volume having least one inlet opening, and at least one outlet opening in fluid communication with the fluid intake. A primary filter is supported on the primary frame and covers the inlet opening such that fluid passes into the enclosed volume through the primary filter. The secondary frame is located within the volume enclosed by the primary frame. A secondary filter is supported on the secondary frame and defines an enclosed flow passage in communication with the outlet opening, such that fluid passes into the at least one outlet opening through the secondary filter and the enclosed flow passage.
A Canned Rotodynamic Flow Machine For A Molten Salt Nuclear Reactor And An Active Magnetic Bearing For Use In A Flow Machine For A Molten Salt Nuclear Reactor
A canned rotodynamiic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor, comprising an impeller (6) arranged in a volute (3), with an inlet (4) and an outlet (5) for the working fluid, an induction or reluctance motor or generator comprising a stator (10) and a rotor (8), a can (18) separating a working fluid area in which the rotor (8) is arranged from a dry area containing the stator (10). The rotor (8) is operably coupled to the impeller (6). The stator (10) comprises stator windings for inducing a magnetic field that penetrates the rotor (8). The stator windings are distributed in slots (11) arranged in the stator (10). The part of the stator windings inside the slots is formed by one or more electrically conductive solid bars (12). An active magnetic bearing for use in a canned rotor dynamic flow machine for a molten salt nuclear reactor, comprising a stator (110,210) and a rotor (108,208). The said stator (108,208) comprises stator windings for inducing a magnetic field that penetrates the rotor (108,208). The stator windings are distributed in one or more slots arranged in the stator. The part of the stator windings inside said one or more slots is formed by one or more electrically conductive solid bars.
A Canned Rotodynamic Flow Machine For A Molten Salt Nuclear Reactor And An Active Magnetic Bearing For Use In A Flow Machine For A Molten Salt Nuclear Reactor
A canned rotodynamiic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor, comprising an impeller (6) arranged in a volute (3), with an inlet (4) and an outlet (5) for the working fluid, an induction or reluctance motor or generator comprising a stator (10) and a rotor (8), a can (18) separating a working fluid area in which the rotor (8) is arranged from a dry area containing the stator (10). The rotor (8) is operably coupled to the impeller (6). The stator (10) comprises stator windings for inducing a magnetic field that penetrates the rotor (8). The stator windings are distributed in slots (11) arranged in the stator (10). The part of the stator windings inside the slots is formed by one or more electrically conductive solid bars (12). An active magnetic bearing for use in a canned rotor dynamic flow machine for a molten salt nuclear reactor, comprising a stator (110,210) and a rotor (108,208). The said stator (108,208) comprises stator windings for inducing a magnetic field that penetrates the rotor (108,208). The stator windings are distributed in one or more slots arranged in the stator. The part of the stator windings inside said one or more slots is formed by one or more electrically conductive solid bars.
Nuclear power plant and method for operating a nuclear power plant
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.
Nuclear power plant and method for operating a nuclear power plant
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.