| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376282000 |
Emergency core coolant systems (e.g., injecting coolant into reactor or pipe systems)
| 69 |
| 376298000 |
Auxiliary heat removal structure
| 52 |
| 376305000 |
Corrosion or damage prevention
| 43 |
| 376287000 |
Shield or barrier between radiation or heat source and object to be protected (e.g., insulation, thermal shield)
| 32 |
| 376283000 |
Pressure suppression and relief
| 28 |
| 376280000 |
Core catchers
| 14 |
| 376307000 |
With pressurizer means | 4 |
| 20090141850 | PRESSURIZED WATER REACTOR PRESSURIZER HEATER SHEATH - A pressurizer whose heater sheaths are conditioned to reduce the residual stresses resulting from cold working during manufacture. After material conditioning, the heater sheath undergoes a surface conditioning treatment to add outer surface compressive stresses. | 06-04-2009 |
| 20140192948 | PASSIVE DEVICE REGULATING PRESSURE IN A CHAMBER, CHAMBER AND ASSOCIATED INSTALLATION - This device comprises a spray assembly ( | 07-10-2014 |
| 20150110236 | NUCLEAR STEAM SUPPLY SYSTEM - A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel. | 04-23-2015 |
| 20150332797 | DEVICE FOR HEATING A PRESSURISER - An induction heating device for a pressuriser of a pressurized water nuclear reactor, which pressuriser includes an enclosure having an inner wall made of magnetic material, the induction heating device including a heating module having a winding mounting, and a winding of conductive wire wound around the winding mounting, the winding generating a magnetic field when an alternating electric current passes therethrough; and a module mounting that engages with an attachment device configured to removably attach the heating module to the module mounting, the module mounting being configured to position the heating module outside of the inner wall of the enclosure of the pressuriser in a position that makes it possible to heat the inner wall of the pressuriser by magnetic induction when an electric current passes through the winding of the heating module. | 11-19-2015 |
| 376300000 |
Recombiners | 3 |
| 20100296619 | Safety System for a Nuclear Plant and Nuclear Plant with a Safety System - A safety system for a nuclear plant includes a plurality of catalytic recombiner elements each triggering a recombination reaction with oxygen when hydrogen is entrained in an onflowing gas flow, so that reliable elimination of the hydrogen from the gas mixture is ensured with an especially high degree of operational safety even based on comparatively extreme conditions or scenarios of the aforementioned type. The recombiner elements and/or the flow paths each connecting two recombiner elements on the gas side are configured in such a way that a pressure pulse triggered in the gas medium by an ignition during the recombination reaction in a first recombiner element triggers a gas displacement process having a flow rate of at least 5 m/s in the onflow region of a second, adjacent recombiner element. A nuclear plant with a safety system is also provided. | 11-25-2010 |
| 20120063560 | DEVICES AND METHODS FOR MANAGING NONCOMBUSTIBLE GASSES IN NUCLEAR POWER PLANTS - Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein. | 03-15-2012 |
| 20140064427 | GAS TREATMENT EQUIPMENT OF NUCLEAR POWER PLANT - At the time of loss of coolant accident, when station blackout occurs, hydrogen, radioactive nuclides, and steam are discharged from a broken portion of a pipe connected to a reactor pressure vessel into the primary containment vessel. A passive autocatalytic hydrogen treatment apparatus installs a catalytic layer and heat exchanger tubes of a heat exchanger in a casing. High-temperature steam including hydrogen and radioactive nuclides is supplied into the heat exchanger tubes and heats gas supplied into the casing | 03-06-2014 |
| 376302000 |
Core restraint means | 3 |
| 20100150298 | CORE SHROUD CORNER JOINTS - A core shroud is provided, which includes a number of planar members, a number of unitary corners, and a number of subassemblies each comprising a combination of the planar members and the unitary corners. Each unitary corner comprises a unitary extrusion including a first planar portion and a second planar portion disposed perpendicularly with respect to the first planar portion. At least one of the subassemblies comprises a plurality of the unitary corners disposed side-by-side in an alternating opposing relationship. A plurality of the subassemblies can be combined to form a quarter perimeter segment of the core shroud. Four quarter perimeter segments join together to form the core shroud. | 06-17-2010 |
| 20100246744 | APPARATUS AND SYSTEM FOR DAMPENING THE VIBRATION EXPERIENCED BY AN OBJECT - An embodiment of the present invention may reduce the level of vibration experienced by a line, such as, but not limiting of, a pipe, a cable, tubing, or the like, that is connected to at least one separate structure. For example, but not limiting of, the structure includes: a reactor pressure vessel, a feedwater sparger pipe, steam generator, a pipe, a pressure vessel, a heat exchanger, a pump, a condenser, a tank, or the like. An embodiment of the present invention may provide support and a preload to the line at a new location or may replace an existing support, such as, but not limiting of, a weld; which may alter the natural frequencies to avoid resonance from occurring when the structure(s) is excited. | 09-30-2010 |
| 20150364222 | NUCLEAR REACTOR SUPPORT AND SEISMIC RESTRAINT - A nuclear reactor is supported by a primary support anchored to a civil structure and defining a reactor support plane located below the center of gravity of the nuclear reactor. A lateral seismic support engages the nuclear reactor below the reactor support plane to prevent lateral motion of the nuclear reactor. In one approach a flange, protrusion, or ledge of the reactor pressure vessel rests on a support engagement surface, a seismic rotational restraint assembly prevents the nuclear reactor from rotating during a seismic event, and a liftoff prevention assembly prevents vertical liftoff of the flange, protrusion, or ledge of the reactor pressure vessel from the support engagement surface. The lateral seismic support may comprise a pin connected with the bottom of the reactor pressure vessel engaging a pin socket connected with or formed in a floor of the civil structure of the radiological containment containing the nuclear reactor. | 12-17-2015 |
| 376285000 |
Expansion means (e.g., shock absorbers, roller bearings) | 2 |
| 20110158372 | SHOCK-ABSORBING DEVICE FOR FUEL ASSEMBLY AND FUEL ASSEMBLY HOUSING CONTAINER - A fuel assembly | 06-30-2011 |
| 20140219410 | FOUNDATION STRUCTURE OF REACTOR CONTAINMENT VESSEL - In the foundation structure of a reactor containment vessel, a lower foundation plate provided on a ground, an upper foundation plate provided over the lower foundation plate, a base isolation device inserted between the upper foundation plate and the lower foundation plate, and a reactor containment vessel provided on the upper foundation plate are provided. The ends of reverse U-shaped tendons serving as the lower structures of the reactor containment vessel are fixed to the lower surface of the upper foundation plate through the upper foundation plate, which makes it possible to simplify a structure and reduce a construction cost. | 08-07-2014 |
| Entries |
| Document | Title | Date |
|---|
| 20090161812 | EVACUATED CONTAINMENT VESSEL FOR A NUCLEAR REACTOR - A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel. | 06-25-2009 |
| 20090245452 | Method and apparatus for mitigating vibration in a nuclear reactor component - A device is provided for mitigating vibration in a component of a nuclear reactor by removing vibration energy. To reduce vibration in the component, a device operatively connected to the component and including a magnet may be actuated within a conductive cylinder. This actuation may generate one or more eddy currents providing a damping function for removing vibration energy from the component, so as to alter vibration characteristics of the component. | 10-01-2009 |
| 20100246743 | STEAM FLOW VORTEX STRAIGHTENER - An embodiment of the present invention provides an apparatus for reducing the magnitude or frequency of flow-induced vibrations. An embodiment of the present invention may be integrated with at least one structure of a reactor pressure vessel of a nuclear reactor. Other embodiments of the present invention may be integrated with other systems that require a dampening of and/or frequency change in the flow-induced vibrations. For example, but not limiting of, the other pressure vessels including: a steam generator, a heat exchanger, a condenser, a boiler, or the like. | 09-30-2010 |
| 20100329409 | DRAIN SUMP OF NUCLEAR REACTOR CONTAINMENT VESSEL - A drain sump of a reactor containment vessel having a containment vessel floor down below a reactor pressure vessel, and includes a heat-proof sump cover and two or more drain flow paths. The drain sump is arranged inside the containment vessel floor. The heat-proof sump cover has a thickness, and covers an upper part of the drain sump. The thickness allows a top surface of the sump cover to lie in the same surface as a top surface of the containment vessel floor. The drain flow paths pass through the sump cover in a thickness direction to flow water therethrough and solidify a molten corium therein. The molten corium is produced in the unlikely event of a severe accident. | 12-30-2010 |
| 20120207261 | Nuclear Power Facility - A nuclear island includes at least one nuclear reactor. A turbine island includes at least a turbine building housing at least one turbine driven by steam generated by the nuclear reactor. A protected area has a perimeter protected by at least one fence. An isolation zone surrounds the protected area and includes intrusion detection devices configured to detect unauthorized approach toward the protected area. The nuclear island is disposed inside the protected area, and the turbine island is disposed outside of and spaced apart from the protected area. | 08-16-2012 |
| 20130208845 | METHOD FOR FILLING WATER INTO A MAIN CIRCUIT OF A NUCLEAR REACTOR, AND CONNECTION DEVICE FOR IMPLEMENTING SAID METHOD - The method for filling water into and changing the air of a main circuit of a water-cooled nuclear reactor includes a step of placing a connection and fluid isolation device which is connected to a hot leg of each cooling loop of the main circuit so as to substantially insulate, from inside the vessel, the assembly of hot legs. The method also includes a step of injecting water through an injection circuit on at least one hot leg until each cooling loop is filled with water having changed the air from a steam generator and until the water level in the vessel reaches above the side openings of the vessel that correspond to the loops, after which the connecting device is taken out of the vessel. The connecting device is capable of using telescopic connection elements. | 08-15-2013 |
| 20130272471 | ISLAND MODE FOR NUCLEAR POWER PLANT - A nuclear power plant comprises a pressurized water reactor (PWR) and a steam generator driving a turbine driving an electric generator. A condenser condenses steam after flowing through the turbine. Responsive to a station blackout, the nuclear power plant is electrically isolated and a bypass valve is opened to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine. The thermal power output of the PWR is gradually reduced over the transition time interval. After opening, the bypass valve is gradually closed over the transition time interval. A supplemental bypass valve may also be opened responsive to the station blackout to convey supplemental bypass steam flow from the steam generator to a feedwater system supplying secondary coolant feedwater to the steam generator. The supplemental bypass steam flow does not flow through the turbine and does not flow through the condenser. | 10-17-2013 |
| 20140064426 | SYSTEM AND METHOD FOR IMPLEMENTING UNIFIED COMPUTER-BASED MANAGEMENT OF FIRE SAFETY-RELATED RISK AND COMPENSATORY MEASURES MANAGEMENT IN NUCLEAR POWER PLANTS - A computer-implemented system and method for managing operations in a nuclear power plant generates an electronic request for a permit to perform work in the plant, performs a risk assessment using a rules engine to determine a level of fire risk posed by the work, automatically determines one or more compensatory measures to provide protection against the level of fire risk posed by work, generates a risk score based the probabilistic assessment, and generates electronic authorization for the permit based on the risk score. | 03-06-2014 |
| 20140301522 | CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR - Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like. | 10-09-2014 |
| 20140301523 | EARTHQUAKE-RESISTANT REINFORCEMENT ASSEMBLY - An earthquake-resistant reinforcement assembly according to one embodiment of the present invention comprises: a rod of which one end is hinge-coupled to an upper structure; a combination pin which is formed at the other end of the rod and is extended to diametrically cross the rod; and a bracket which is provided on a partition wall of a nuclear reactor containment building and is coupled with the other end, wherein the bracket can withstand a tensile load and a torsional load by including first and second members which face each other and are extended in parallel to load the rod thereon, and groove portions which are formed at the first and second members to be coupled with the combination pin to form the shape of a double bracket. | 10-09-2014 |
| 20150117585 | Gas Supply Apparatus and Air or Nitrogen Supply Apparatus of Nuclear Plant - A gas supply apparatus of the present invention includes: an operating valve that is placed in the middle of a piping for letting at least gas in a plant flow and that operates a valve main body by the gas flowing in the piping; a first electromagnetic valve that is placed in the middle of the piping and that opens or closes a flow of the gas to the operating valve; and a gas supply source that supplies the first electromagnetic valve with the gas. A gas discharge line of the first electromagnetic valve has a switching valve placed therein and has a second electromagnetic valve placed between the switching valve and the gas supply source. The switching valve switches between a gas discharge from the first electromagnetic valve and a gas supply to the first electromagnetic valve. When a power source is lost, the switching valve is switched to connection to the gas supply source so as to supply the first electromagnetic valve with the gas. At the time of a normal operation, the second electromagnetic valve opens a gas discharge line side and closes a switching valve side, and when the power source is lost, the second electromagnetic valve opens the switching valve side and closes the gas discharge line side. In this way, even when the power source is lost, an operating valve such as an air-operated valve can not only be operated remotely but also be operated safely by a remote operator. | 04-30-2015 |
| 20150131768 | NUCLEAR FUEL ROD CLADDING INCLUDING A METAL NANOMATERIAL LAYER - A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers. | 05-14-2015 |
| 20160019988 | Containment for a water cooled and moderated Nuclear Reactor - In this invention a novel containment for a water cooled and moderated nuclear reactor is disclosed which incorporates two or more separate containment zones. These zones are constructed in such a manner that a leak or break in the reactor coolant system located within one zone will remain confined within this particular zone, so that no adverse ambient conditions of pressure, temperature, and humidity will propagate to any of the other zones. The separation between zones is achieved by having a partition plate extending from a circumference of the inside surface of the containment envelope towards the outside surface of the reactor coolant system where the partition plate is attached to one of the main components of the reactor coolant system. For example, and as presented in some of the embodiments, this can be the reactor pressure vessel. The partition is designed to the same pressure and temperature conditions as the containment vessel envelope so as to ensure a substantially leak tight and permanent separation between adjacent zones. | 01-21-2016 |
| 20160027536 | MOBILE HEAT PIPE COOLED FAST REACTOR SYSTEM - A mobile heat pipe cooled fast nuclear reactor may be configured for transportation to remote locations and may be able to provide 0.5 to 2 megawatts of power. The mobile heat pipe cooled fast reactor may contain a plurality of heat pipes that are proximate to a plurality of fuel pins inside the reactor. The plurality of heat pipes may extend out of the reactor. The reactor may be configured to be placed in a standard shipping container, and may further be configured to be contained within a cask and attached to a skid for easier transportation. | 01-28-2016 |
| 20160042818 | OUTLET NOZZLE OF NUCLEAR REACTOR - The present invention relates to an outlet nozzle of a nuclear reactor. More specifically, in the outlet nozzle of a nuclear reactor which is provided to a reactor vessel and into which the coolant discharged from the nozzle of a structure in the reactor is introduced, the outlet nozzle of a nuclear reactor has an inclination part formed at one side of the outlet nozzle such that the inclination part is inclined at a predetermined angle from the outside end to the inside thereof. The present invention has an effect, wherein the one side of the outlet nozzle into which the coolant is introduced from the nozzle of a structure in the nuclear reactor is inclined or rounded such that an inspection robot (ASME Sec XI IWB-3512) for inspecting the presence of a defect in the coupling state of the reactor while moving along the inside surface of the reactor vessel in the reactor can move to the lower side of the reactor, and thus the volumetric inspection of the reactor by the inspection robot can be freely and continuously advanced such that the volumetric inspection can be carried out to 100% without any excluded portion for welded parts. In addition, the stability of the nuclear reactor can be more effectively verified as the volumetric inspection is carried out to 100%. | 02-11-2016 |
| 20160109185 | ENERGY STORAGE SYSTEM - Energy storage system regulating power output of a power generation plant that has a heat exchanger, primary circuit and secondary circuit, primary circuit directs primary fluid flow to components of a primary region and secondary circuit directs a secondary fluid flow to components of a secondary region, the heat exchanger is arranged so the secondary fluid flow is heated from the primary fluid flow. Energy storage arrangement makes a vessel for storing secondary fluid. Fluid transfer arrangement connects the vessel and is connectable to the heat exchanger of the power generation system to arrange the fluid transfer arrangement in fluid communication with the heat exchanger and the vessel. Bidirectional flow arrangement configured to control flow direction of fluid between the vessel and fluid transfer arrangement to selectively store heat energy from the heat exchanger in the vessel, and selectively transfer heat energy stored in the vessel to the heat exchanger. | 04-21-2016 |
| 20160125964 | SEISMIC ATTENUATION SYSTEM FOR A NUCLEAR REACTOR - A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel may include a bottom head. Additionally, the system may include a base support that is configured to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device may be located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel may be attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel. | 05-05-2016 |
| 20160379723 | SYSTEM FOR PURIFYING A GASEOUS MEDIUM OF HYDROGEN AND METHOD FOR THE USE THEREOF - Disclosed is a hydrogen igniter for igniting hydrogen contained in a gaseous medium, said hydrogen igniter comprising a housing with openings for the supply and discharge of a gaseous medium, and a filler in the form of bismuth oxide and/or lead oxide, disposed inside the housing. Also disclosed are a system for purifying a gaseous medium of hydrogen having such a hydrogen igniter, and a method for the repeated use of such a system. The igniter and the system can be used in a nuclear reactor facility. | 12-29-2016 |
| 20180025795 | SEISMIC ATTENUATION SYSTEM FOR A NUCLEAR REACTOR | 01-25-2018 |
