| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376383000 | Fluid is a gas | 20 |
| 20100086096 | Gas Turbine Plant - A gas turbine plant, wherein a first gas turbine positioned coaxially with a compressor and a second gas turbine positioned coaxially with a generator are rotated by a coolant heated by heat energy provided by the fission of a coated particle fuel. The rotational speed of the first gas turbine is controlled by controlling a flow in the bypass passage of the second gas turbine. | 04-08-2010 |
| 20110305310 | EQUIPMENT AND SYSTEM FOR PROCESSING A GASEOUS MIXTURE BY PERMEATION - The invention relates to an equipment and a system for processing a gaseous mixture by permeation. The equipment of the invention includes m*n separation modules P | 12-15-2011 |
| 376384000 | Wherein the gas is steam | 6 |
| 20120002776 | Dry coolant for primary stage of nuclear reactors - Nuclear reactors are customarily cooled by water from a natural source in the area. Water brings impurities to and surrounds the fuel rods with a mix of materials, some of which react with the fuel rod contents. Changing the coolant to a pure, inert gas sourced from its cryogenic liquid form with ambient pressure gives greater control of the situation and enables running the reactor at the critical point of water so the cycle of coolant is released to the purifier carrying whatever material is expelled by the fuel rods and the steam cycle leaves the radiator from the reactor chamber as steam leaving little, if any, water release from the nuclear plant with no impurities but what is emitted by the fuel rods themselves contaminating the rod environment. Eliminating the hot water surrounding the plant, security of the Nuclear site is greater since infrared sighting is prevented with shielding just the reactor. Reactor byproducts can be separated and isolated to protect the environment and provide radioactive reagents for research. Liquid Nitrogen availability also provides the fixed fire and crises control for the entire facility eliminating water damage and electrical arcing keeping the computer and control system functional through crises situations. It is predicted that running the Nuclear reactor at 374° C., the critical point of water, can make a smaller system for the same level of power production from a steam generator and can provide mobility of the system is small scale. | 01-05-2012 |
| 20130044853 | FEED WATER AND STEAM HEADER AND NUCLEAR REACTOR HAVING THE SAME - A feed water and steam header equipped to a feed water nozzle or a steam nozzle of a reactor vessel in a steam generator for an integrated nuclear reactor is provided. The feed water and steam header may include a nozzle connection portion connected to a steam nozzle or a feed water nozzle of a reactor vessel, a header flange protruded outward from a lower part of the nozzle connection portion, and a tube connection portion disposed on two pipelines branched from the nozzle connection portion and connected to a tube of the steam generator. | 02-21-2013 |
| 20130336442 | PRESSURIZED WATER REACTOR COMPACT STEAM GENERATOR - A steam generator system for a pressurized water reactor which employs an external to containment steam drum and recirculation loop piping. The steam generator system changes the arrangement of a typical pressurized water reactor recirculation steam generator by relocating the functions of steam separation and feedwater preheating outside of the reactor coolant system. The steam generator system and thermal hydraulic conditions are selected in order to minimize the size of the steam generator heat exchanger component volume inside of the containment. The external steam drum component can be isolated in accident conditions when desired and is used as a source of secondary fluid inventory for improved decay heat removal capability and tolerance for loss of feedwater events. Thus, the steam generator component volume inside of the containment is reduced and the amount of maintenance required for the reactor coolant system components are similarly reduced. | 12-19-2013 |
| 20140334593 | SYSTEM AND METHOD FOR STORING ENERGY IN A NUCLEAR POWER PLANT - A method for storing the energy of a nuclear power plant in which the nuclear core is cooled by gases or liquid heat transfer media. The hot heat transfer liquid is stored directly in storage tanks. When needed, it is used for heating a power plant. The heat of a compressed gas heat transfer medium such as helium is stored by passing the compressed gas through tanks filled with heat-resistant solids and recovered by passing the same type of gas in a second circuit in a reverse direction. Through the hot tanks to the power plant and back. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way. | 11-13-2014 |
| 20160005498 | 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 ( | 01-07-2016 |
| 20160087184 | ARRANGEMENT AND CONTROL OF THERMOELECTRIC POWER GENERATION CELLS - A device is disclosed for generating electricity and is of particular use in the event of a Beyond Design Basis Event at a nuclear power plant. The device includes a first string including a first plurality of thermoelectric generator cells, each of the thermoelectric generator cells of the first plurality operable to generate a voltage and current across a pair of electrical terminals, based upon a temperature differential between two fluids, a second string including a second plurality of thermoelectric generator cells and circuitry adapted to control, dependent upon the temperature differential between the two fluids a switch between a first configuration and a second configuration. In the first configuration the two strings are electrically in parallel and the second configuration, the two strings are electrically in series. | 03-24-2016 |
| 376385000 | Having specified flow path or pattern within reactor core | 2 |
| 20090252277 | Upper Plenum Structure of Cooled Pressure Vessel for Prismatic Very High Temperature Reactor - An upper plenum structure of a cooled pressure vessel for a prismatic very high temperature reactor which secures a space for coolant to supply to a core and also supports an upper reflector located inside a graphite structure on top of the core. The upper plenum structure includes a cavity structure where the coolant goes down in the upper plenum structure, a plurality of upper reflector supports formed with the cavity and supporting the upper reflector located on top thereof, and a plurality of coolant distributing blocks. Each of the coolant distributing blocks is coupled with a bottom portion of a respective one of the upper reflector supports and is located on top of the core in order to distribute the coolant collected in a cavity, formed by the upper reflector support, to the core. The coolant distributing blocks cooperate with the upper reflector supports to define the cavity structure. | 10-08-2009 |
| 376386000 | Plural separate loops | 1 |
| 20120314830 | INSTALLATION FOR PRODUCING POWER FROM A GAS-COOLED FAST NUCLEAR REACTOR - A power production installation including a primary circuit containing gas passing via a nuclear reactor, via a first heat exchanger, and via a blower. A secondary circuit containing incondensable gas passes via the first heat exchanger, and via a turbine and a compressor fitted on the same shaft. The blower is driven by the shaft. The gases in the primary and secondary circuits are of the same nature, and the pressure in the secondary circuit is automatically regulated by the pressure in the primary circuit. | 12-13-2012 |
| 376391000 | Manipulated or used exterior of the reactor core | 10 |
| 20090122943 | ELECTRICITY AND STEAM GENERATION FROM A HELIUM-COOLED NUCLEAR REACTOR - Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium, expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator. | 05-14-2009 |
| 20100074390 | METHOD FOR WEATHER MODIFICATION AND VAPOR GENERATOR FOR WEATHER MODIFICATION - A nuclear fusion reactor ( | 03-25-2010 |
| 20100202582 | SYSTEM AND METHOD FOR STORING ENERGY IN A NUCLEAR POWER PLANT - A method of storing heat includes moving a portion of a heated fluid from at least one reactor core to at least one tank having solid media, storing heat from the portion of the heated fluid in the solid media, and transferring the stored heat from the solid media to a fluid that can be used by a power plant to generate electrical energy. A system for storing heat in a nuclear power plant includes at least one tank comprising solid media structured and arranged to store heat and an arrangement structured and arranged to pass a first fluid through the at least one tank, transfer heat from the first fluid to the solid media, store the heat in the solid media, and transfer the heat from the solid media to a second fluid. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way. | 08-12-2010 |
| 376392000 | With jet pump | 7 |
| 20120155598 | METHOD AND APPARATUS FOR A RISER PIPE REPAIR WITH COMPRESSION - A method and apparatus for repairing and/or reinforcing a Boiling Water Reactor (BWR) jet pump riser pipe. The repair includes attaching two collars to the riser pipe using match drilling to drill holes through the collars and the riser pipe and plugging the holes with expandable plugs. Support columns are attached to the collars. Brace supports are slideably attached to the support columns. Gaps between each brace support and its respective collar are then narrowed as ratchet bolts may apply a force that pulls downward on an upper collar and pulls upward on a lower collar, thereby exerting a compression force on the riser pipe. A clamp assembly may also be located between the two collars that applies a hoop force on the riser pipe. | 06-21-2012 |
| 20120155599 | METHOD AND APPARATUS FOR AN EXPANDING SPLIT BUSHING PIPE PLUG ASSEMBLY - A method and apparatus for securely fastening a pipe collar or a bracket to a riser pipe of a boiling water reactor (BWR) jet pump assembly. A pipe plug assembly includes an angled pipe plug that acts as a wedge to expand a bushing assembly as the pipe plug is drawn into the overall pipe plug assembly. Expansion of the bushing assembly allows a tight tolerance to exist between an outer diameter of the pipe plug and an inner diameter of the collar/bracket and riser pipe. Expansion of the bushing assembly allows a straight hole to be match drilled into the collar/bracket and riser pipe, thereby avoiding a more complicated tapered hole to be drilled into the collar/bracket and riser pipe. An ensuing tight fit between the pipe plug assembly, the collar/bracket and the riser pipe mitigates vibration of components and minimizes leakage to acceptable levels for use in the flooded environment of the annulus region where the jet pump assembly exists in the BWR. | 06-21-2012 |
| 20120288053 | METHOD AND APPARATUS FOR A BWR JET PUMP INLET MIXER COMPLIANT STOP - A method and apparatus for a boiling water reactor (BWR) jet pump inlet mixer compliant stop. The inlet mixer compliant stop may be installed in a pocket area between a riser pipe and an inlet mixer of a BWR jet pump assembly. The inlet mixer compliant stop includes a main body and a foot that are separated via the tightening of one or more jacking bolts used to connect the main body and the foot. A cold spring attached to the main body provides a lateral force that is imparted on the inlet mixer, to force the inlet mixer away from a centerline of the riser pipe. A precise lateral force may be imparted on the inlet mixer by gauging a width of a gap between opposing bosses on a front face of the main body and a distal end of the cold spring. The inlet mixer compliant stop imparts a greater lateral force on the inlet mixer as the jacking bolts are tightened, further separating the main body from the foot, as the gap between the opposing bosses is reduced. | 11-15-2012 |
| 20130301787 | PRESSURIZED WATER REACTOR WITH REACTOR COLLANT PUMPS COMPRISING TURBO PUMPS DRIVEN BY EXTERNAL PUMPS - A pressurized water reactor (PWR) includes a pressure vessel containing a nuclear core comprising a fissile material immersed in primary coolant water. A reactor coolant pump (RCP) is configured to pump primary coolant water in the pressure vessel. The RCP includes a hydraulically driven turbo pump disposed in the pressure vessel. The turbo pump includes an impeller performing pumping of primary coolant water in the pressure vessel, and a hydraulically driven turbine mechanically coupled with the impeller to drive the impeller. The RCP may further include a hydraulic pump configured pump primary coolant water to generate hydraulic working fluid that drives the hydraulically driven turbine. The hydraulic pump may be a canned pump having a casing defining a portion of the pressure boundary of the pressure vessel. The casing includes electrical feedthroughs delivering electrical power to the hydraulic pump. | 11-14-2013 |
| 20130301788 | REACTOR COOLANT PUMP SYSTEM INCLUDING TURBO PUMPS SUPPLIED BY A MAINFOLD PLENUM CHAMBER - A nuclear reactor includes a nuclear core comprising a fissile material, and a pressure vessel containing the nuclear core immersed in primary coolant water. Turbo pumps disposed in the pressure vessel provide active circulation of primary coolant water in the pressure vessel. Each turbo pump includes a turbine driving an impeller. A manifold plenum chamber is disposed in the pressure vessel, and is in fluid communication with inlets of the turbines of the turbo pumps. An electrically driven pump operatively connected with the manifold plenum chamber to pressurize the manifold plenum chamber with primary coolant water. The turbo pumps may be disposed in openings passing through the manifold plenum chamber. The pressure vessel may be vertically oriented and cylindrical, with a cylindrical riser oriented coaxially inside, and the manifold plenum chamber may be annular and disposed in a downcomer annulus defined between the cylindrical riser and the cylindrical pressure vessel. | 11-14-2013 |
| 20130301789 | REACTOR COOLANT PUMP SYSTEM WITH ANNULAR FLOW TURBO PUMP - A reactor coolant pump (RCP) generates primary coolant flow in a nuclear reactor. The RCP includes a flow amplification device, such as a turbo pump, disposed in the pressure vessel of the nuclear reactor, and an electrically driven pump (e.g. a centrifugal pump). The inlet of the electrically driven pump receives primary coolant water from the pressure vessel and the outlet discharges into the driving inlet of the flow amplification device (e.g. into the turbine of a turbo pump) such that the centrifugal pump drives the flow amplification device to pump primary coolant water. A divider is disposed in the pressure vessel and separates the pumping inlet of the flow amplification device from the pumping outlet of the flow amplification device. The electrically driven pump may include hydraulic drive shaft bearings and starting mechanical drive shaft bearings that disengage at operating speed due to axial shift of the drive shaft. | 11-14-2013 |
| 20130301790 | PRESSURIZED WATER REACTOR WITH REACTOR COOLANT PUMP SYSTEM INLCUDING JET PUMPS - An integral pressurized water reactor (PWR) includes a cylindrical pressure vessel, a cylindrical central riser disposed coaxially inside the cylindrical pressure vessel wherein a downcomer annulus is defined between the cylindrical central riser and the cylindrical pressure vessel, a nuclear core comprising a fissile material, and a steam generator disposed in the downcomer annulus. A reactor coolant pump (RCP) includes a jet pump disposed in the downcomer annulus above or below the steam generator, and a hydraulic pump configured to pump primary coolant into a nozzle of the jet pump. The hydraulic pump includes an electric motor mounted externally on the pressure vessel. | 11-14-2013 |
