| 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 |
| 20080212733 | Nuclear power plant using nanoparticles in emergency systems and related method - A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided. | 09-04-2008 |
| 20080219395 | Nuclear power plant using nanoparticles in emergency situations and related method - A nuclear power plant provides for delivery of nanoparticles to coolant found in the containment, for example during severe accident scenarios. The nanoparticles advantageously can be delivered passively or actively independently of any emergency core cooling system. The nanoparticle supply can include for example tanks storing nanofluids or solid nanoparticles, or dissolvable paints containing nanoparticles. Methods for providing the nanoparticles are also provided. | 09-11-2008 |
| 20080219396 | Nuclear power plant using nanoparticles in closed circuits of emergency systems and related method - A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form to improve heat transfer and reduce corrosion is provided. The nanoparticles are delivered to a closed cooling circuit such as a CCWS. Methods for providing the nanoparticles are also provided. | 09-11-2008 |
| 20080285701 | Injection System and Associated Operating Method - A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid. | 11-20-2008 |
| 20080317193 | EMERGENCY CORE COOLING SYSTEM - An emergency core cooling system is provided with a hybrid safety system composed of an active safety system and a static safety system for ensuring the safety against a severe natural phenomenon such as a giant earthquake and a mega hurricane. An emergency core cooling system for a boiling water reactor includes four safety divisions in total: three safety divisions for an active safety system having a high pressure reactor core cooling system, a low pressure reactor core cooling system, a residual heat removal system, and an emergency diesel generator; and one safety division for a static safety system having an isolation condenser, a gravity drop reactor core cooling system, and a static containment vessel cooling system. | 12-25-2008 |
| 20090060112 | BOILING WATER NUCLEAR REACTOR AND EMERGENCY CORE COOLING SYSTEM OF THE SAME - A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool. | 03-05-2009 |
| 20090129530 | PASSIVE EMERGENCY FEEDWATER SYSTEM - A power module assembly includes a reactor vessel containing a reactor core surrounded by a primary coolant. A containment vessel is adapted to be submerged in a containment cooling pool and to prohibit a release of the primary coolant outside of the containment vessel. A secondary cooling system is configured to remove heat generated by the reactor core. The heat is removed by circulating liquid from the containment cooling pool through the primary coolant. | 05-21-2009 |
| 20090232267 | EMERGENCY CORE COOLING SYSTEM HAVING CORE BARREL INJECTION EXTENSION DUCTS - An emergency core cooling system directly injects emergency core cooling water, which is supplied from a high-pressure safety injection pump or a safety injection tank for a pressurized light water reactor, into a reactor vessel downcomer. A pipe connector is completely removed from between each direct vessel injection nozzle and each injection extension duct installed on an outer surface of the core barrel, which are opposite to each other. An emergency core cooling water intake port, through which the water is injected from each direct vessel injection nozzle, is formed on the surface of each injection extension duct facing an axis of each direct vessel injection nozzle. Thereby, a structure in which a jet of the emergency core cooling water flows into the injection extension ducts is adopted in a hydraulic connection fashion. | 09-17-2009 |
| 20090279657 | SAFETY INJECTION TANK WITH GRAVITY DRIVEN FLUIDIC DEVICE - A safety injection tank, used for quickly injecting emergency core cooling water (ECCW) to a reactor vessel in the case of a cold leg large break accident (CLLBA) in a pressurized water reactor (PWR), is disclosed. The safety injection tank has a gravity-driven fluidic device configured to efficiently change the ECCW injection mode from a high flow injection mode to a low flow injection mode. The gravity-driven fluidic device includes a spring placed in the upper end of the vertical pipe, and a vertically movable water tub placed on the spring so as to be movable in a vertical direction. When ECCW contained in the pressure vessel is discharged and the water level is reduced lower than the height of the tub, the tub is moved downwards such that the lower surface thereof comes into contact with the vertical pipe and closes the high flow inlet port. | 11-12-2009 |
| 20100046692 | INJECTION SYSTEM AND ASSOCIATED OPERATING METHOD - A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid. | 02-25-2010 |
| 20100124303 | STEAM GENERATOR FLOW BY-PASS SYSTEM - A nuclear reactor module includes a reactor vessel and a reactor housing mounted inside the reactor vessel, wherein the reactor housing comprises a shroud and a riser located above the shroud. The nuclear reactor module further includes a heat exchanger proximately located about the riser, and a reactor core located in the shroud. A steam generator by-pass system is configured to provide an auxiliary flow path of primary coolant to the reactor core to augment a primary flow path of the primary coolant out of the riser and into the shroud, wherein the auxiliary flow path of primary coolant exits the reactor housing without passing by the heat exchanger. | 05-20-2010 |
| 20100208859 | DEGASSING VALVE AND CHECK VALVE COMBINATION - A venting-valve/check-valve combination useful for venting non-condensable gases and steam (or a combination) in a liquid pipeline comprises a venting-valve, a check-valve, and a capillary port through which gas can pass, said port having two openings, each valve controlling the opening and closing of one of said openings. | 08-19-2010 |
| 20100226470 | DIRECT VESSEL INJECTION (DVI) NOZZLE FOR MINIMUM EMERGENCY CORE COOLING (ECC) WATER BYPASS - A direct vessel injection (DVI) nozzle for minimum emergency core coolant (ECC) bypass is disclosed. The DVI nozzle is used in a pressurized light water reactor (PLWR) having a reactor vessel with a reactor coolant system in which a coolant flows into the reactor vessel through a cold leg and passes through a reactor core prior to being discharged to the outside of the reactor vessel through a hot leg. The DVI nozzle, provided to directly inject ECC into the reactor vessel to cool the reactor core during a break in the reactor coolant system, such as a cold leg break (CLB) that may occur in the PLWR, is placed on the reactor vessel at a position horizontally offset from the central axis of the hot leg at an angle of 10° to 30° and is involved within a region defined above the central axis of the hot leg by a distance of 1.5 times the sum of diameters of the hot leg and the DVI nozzle. Thus, the DVI nozzle efficiently injects ECC, and remarkably reduces the direct ECC bypass fraction to a broken cold leg and minimizes the amount of direct ECC bypass. | 09-09-2010 |
| 20100239062 | COOLANT WITH DISPERSED NEUTRON POISON MICRO-PARTICLES, USED IN SCWR EMERGENCY CORE COOLING SYSTEM - Disclosed is a coolant with dispersed neutron poison micro-particles, used in a supercritical water-cooled reactor (SCWR) emergency core cooling system. Since the neutron poison micro-particles are uniformly dispersed in the coolant of the emergency core cooling system for a long period time, their fluidity is not lowered even though the polarity of water is changed in a supercritical state. Therefore, the neutron poison micro-particles absorb neutrons produced from nuclear fission in a nuclear reactor core. Accordingly, the neutron poison micro-particles can be appropriately used as a means for controlling neutrons and stopping a nuclear reactor in the SCWR emergency core cooling system. | 09-23-2010 |
| 20100260302 | NUCLEAR REACTOR WITH IMPROVED COOLING IN AN ACCIDENT SITUATION - A nuclear reactor including a vessel configured to hold a reactor core, a primary circuit cooling the reactor, a reactor pit in which the vessel is placed, an annular channel surrounding a lower portion of the vessel in the reactor pit, the channel configured to act as a thermal shield in normal operation and to ascend flow of a liquid in event of an accident, a reserve of liquid capable of filling the reactor pit, a reactor containment, a chamber collecting steam generated at an upper end of the reactor pit, the chamber being separate from the containment, a circulating pump capable of generating a forced convection of the liquid in the annular channel, and a lobe pump or steam piston machine or turbine for actuating the circulating pump and capable of generating forced convection by the collected steam. | 10-14-2010 |
| 20100272226 | BOILING WATER NUCLEAR REACTOR AND EMERGENCY CORE COOLING SYSTEM OF THE SAME - A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool. | 10-28-2010 |
| 20100278294 | EMERGENCY CORE COOLING DUCT FOR EMERGENCY CORE COOLING WATER INJECTION OF A NUCLEAR REACTOR - The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct. | 11-04-2010 |
| 20120057668 | REACTOR CONTAINMENT STRUCTURE - The reactor containment structure is provided with a reactor containment vessel, a reactor containment chamber installed inside the reactor containment vessel to contain a nuclear power reactor, a pool installed inside the reactor containment vessel so as to be below the reactor containment chamber adjacently and in which an emergency cooling liquid is stored, an opening part for allowing the emergency cooling liquid to flow from the reactor containment chamber into the pool, a sump installed below the pool, a debris filtering body installed at the sump to filter debris contained in the emergency cooling liquid, a pumping system which sucks the emergency cooling liquid from the sump and discharges the emergency cooling liquid into the reactor containment chamber, and a debris trapping part installed in the pool to trap the debris, wherein the debris trapping part intersects with a flow path of the emergency cooling liquid. | 03-08-2012 |
| 20120076255 | ALTERNATE FEEDWATER INJECTION SYSTEM TO MITIGATE THE EFFECTS OF AIRCRAFT IMPACT ON A NUCLEAR POWER PLANT - The present invention relates to an alternate feedwater injection system to at least partially mitigate the effects of an aircraft impact on a light water nuclear reactor positioned in a reactor building. The light water nuclear reactor has a primary system and a reactor core. The alternate feedwater injection system includes a water storage tank, an injection point into the primary system, a pump capable to transfer water from the water storage tank to the injection point and ultimately to the reactor core. The water storage tank and pump are located external to a reactor building and outside of an identified aircraft impact area or inside the identified aircraft impact area and provided with a means of protection from the aircraft impact. | 03-29-2012 |
| 20120087456 | APPARATUS AND METHOD FOR REINFORCING PIPING ARRANGEMENT OF REACTOR CORE SPRAY SYSTEM - A reinforcing device includes a clamp that is disposed on an outer side of a welded portion of a core spray system piping and holds the core spray system piping at axially symmetrical points on an outer surface thereof, the piping being located on opposite sides of a weld line of the welded portion and also includes a bolt that is provided on the clamp so as to serve as a mechanical fastening mechanism applying a compressive force to the welded portion from the outside of the core spray system piping. | 04-12-2012 |
| 20120213322 | EMERGENCY CORE COOLING SYSTEM AND REACTOR FACILITY - As shown in FIG. | 08-23-2012 |
| 20120243651 | EMERGENCY CORE COOLING SYSTEM FOR PRESSURIZED WATER REACTOR - A pressurized water nuclear reactor (PWR) has an internal pressurizer volume containing a steam bubble and is surrounded by a containment structure. A condenser is disposed inside the containment structure and is operatively connected with an external heat sink disposed outside of the containment structure. A valve assembly operatively connects the PWR with the condenser responsive to an abnormal operation signal such that the condenser condenses steam from the steam bubble while rejecting heat to the external heat sink and returns the condensed water to the PWR. A quench tank contains water with dissolved neutron poison. A valved tank pressurizing path selectively connects the steam bubble to the quench tank to pressurize the quench tank, and a valved soluble poison delivery path selectively connects the quench tank to the PWR such that the quench tank under pressure from the steam bubble discharges water with dissolved neutron poison into the PWR. | 09-27-2012 |
| 20120263268 | PASSIVE HIGH PRESSURE SAFETY INJECTION TANK SYSTEM (HPSIT) FOR RESPONDING TO STATION BLACKOUT (SBO) AND LOSS-OF-COOLANT ACCIDENTS (LOCA) - A high pressure safety injection tank (HPSIT) system includes one safety injection tank (HIT) which replaces a core makeup tank (CMT) and a low pressure (approximately 4.3 Mpa or below) safety injection tank (SIT) and which can shift to and operate on a high pressure (approximately 17 Mpa) operation mode, to enable injection of emergency core coolant into a reactor system both under low pressure (approximately 4.3 Mpa or below) and high pressure (approximately 17 Mpa). | 10-18-2012 |
| 20120281802 | EMERGENCY SYSTEM - An emergency system of nuclear facility includes a gas turbine generator | 11-08-2012 |
| 20120294408 | PASSIVE EMERGENCY FEEDWATER SYSTEM - A power module assembly includes a reactor vessel containing a reactor core surrounded by a primary coolant. A containment vessel is adapted to be submerged in a containment cooling pool and to prohibit a release of the primary coolant outside of the containment vessel. A secondary cooling system is configured to remove heat generated by the reactor core. The heat is removed by circulating liquid from the containment cooling pool through the primary coolant. | 11-22-2012 |
| 20120294409 | TRANSIENT MITIGATION SYSTEM FOR REACTOR - A transient mitigation system for a reactor includes: a reactor core isolation cooling system; and a high pressure flooder system including a high pressure flooder pump and a flooder valve. When the water level of the reactor water in the reactor decreases to a first predetermined water level, the reactor core isolation cooling system is activated to supply the cooling water into the reactor. When the water level in the reactor decreases to the first predetermined water level, the high pressure flooder pump is activated. When the water level in the reactor decreases to a second predetermined water level lower than the first predetermined water level, the flooder valve is opened to inject the cooling water into the reactor. | 11-22-2012 |
| 20130070887 | REACTOR ADAPTED FOR MITIGATING LOSS-OF-COOLANT ACCIDENT AND MITIGATION METHOD THEREOF - Disclosed are a nuclear reactor adapted for mitigating a loss-of-coolant accident and a mitigation method thereof. The nuclear reactor includes a nuclear reactor vessel, a first pipe part connected to the nuclear reactor vessel to supply or drain fluid, and a first opening/closing part connected to the first pipe part. When the first pipe part is broken, the first opening/closing part closes the first pipe part to stop discharge of coolant. A supplementary coolant injection part is connected to the nuclear reactor vessel through a second pipe part. When the second pipe part is broken, a second opening/closing part closes the second pipe part to stop discharge of coolant. | 03-21-2013 |
| 20130114778 | LIQUID METAL COOLED NUCLEAR REACTOR AND HEAT REMOVAL METHOD FOR THE SAME - A liquid metal cooled nuclear reactor includes a reactor vessel, a containment, an air flow path, and an injection unit. The vessel has a reactor core and a coolant for the reactor core. The containment surrounds an outside of the vessel. The air flow path removes heat by flowing air around the containment. The injection unit injects filler in a gap between the vessel and the containment. | 05-09-2013 |
| 20130114779 | APPARATUS FOR CHARGING EMERGENCY BATTERY USING THERMOELECTRIC GENERATION DEVICE IN NUCLEAR POWER PLANT - An apparatus for charging an emergency battery, which provides an emergency power to an emergency core cooling apparatus including an electric pump or a steam pump includes a thermoelectric generation device configured to detect a decay heat and a residual heat produced in a nuclear power plant and configured to convert the detected heat to an electric energy; an electric energy conversion unit connected to the thermoelectric generation device to output a current generated in the thermoelectric generation device as a constant voltage; and the emergency battery configured to store a power outputted from the electric energy conversion unit. | 05-09-2013 |
| 20130121453 | PRESSURIZED WATER REACTOR WITH UPPER PLENUM INCLUDING CROSS-FLOW BLOCKING WEIR - A pressurized water reactor (PWR) comprises: a nuclear core comprising a fissile material; a cylindrical pressure vessel having a vertically oriented cylinder axis and containing the nuclear core immersed in primary coolant water; and a hollow cylindrical central riser disposed concentrically with and inside the cylindrical pressure vessel. A downcomer annulus is defined between the hollow cylindrical central riser and the cylindrical pressure vessel. The hollow cylindrical central riser has a radially expanding upper orifice that merges into an annular divider plate that separates an upper plenum above the annular divider plate from a lower plenum below the annular divider plate. The upper plenum is in fluid communication with the radially expanding upper orifice and the lower plenum is in fluid communication with the downcomer annulus. A weir may extend away from a bottom wall of the lower plenum into the lower plenum. An emergency core cooling system (ECCS) return line nozzle may be arranged to inject water into the upper plenum. A pump support plate spans the inner diameter of the cylindrical pressure vessel and forms a portion of the pressure boundary of the cylindrical pressure vessel, and reactor coolant pumps (RCPs) are supported by the pump support plate. Alternatively, reactor coolant pumps (RCPs) are supported by an arcuate annular ledge formed in the upper portion of the cylindrical pressure vessel. | 05-16-2013 |
| 20130170599 | ASSEMBLY AND METHOD FOR INJECTING WATER CONTAINING A NEURTON-ABSORBING ELEMENT TO COOL A NUCLEAR REACTOR CORE IN A CRISIS SITUATION - An assembly is provided including a mobile structure including a main pipe equipped with a first end intended to be connected to a water supply and a second end intended to be connected to a circuit connected to the primary circuit of the reactor, and including between these two ends in the direction of circulation of the water, a pump, a water heating device, an injector for continuously injecting the powdered neutron-absorbing element into the water of the main pipe, a first mixer for mixing and dissolving powder with water and a controller driving and controlling the flow rate of the water and the flow rate of the powder injected. | 07-04-2013 |
| 20130208846 | Liquid nitrogen emergency cooling system for nuclear plants - The Liquid Nitrogen Cooling System utilizes a continuously recharged, closed-loop system to: generate electricity; charge and pressurize hydraulic bypass and operational equipment; and, provide emergency cooling. | 08-15-2013 |
| 20130235966 | EMERGENCY CORE COOLING SYSTEM AND BOILING WATER NUCLEAR PLANT - An emergency core cooling system is provided with at least four active safety divisions each equipped with a motor-driven active safety system, and at least one passive safety division equipped with passive system that does not require to be electrically driven. The number of active safety divisions is grater than the number of active safety divisions needed during a design basis accident by two or more, and each active safety division is provided with one motor-driven active safety system. The passive safety system can cool the reactor core without being re-supplied with cooling water from the outside during the time period needed for the active safety system subjected to online maintenance to recover if an accident occurred during online maintenance of one active safety system. In an emergency core cooling system for a boiling water nuclear power plant, it is possible to reduce the size of an emergency power source and the number of systems that lose the function caused by an auxiliary cooling system losing the function. | 09-12-2013 |
| 20130251085 | LOW PRESSURE REACTOR SAFETY SYSTEMS AND METHODS - A supplementary injection device is installed in a nuclear power plant to draw coolant and inject coolant using an entraining fluid. The injection device can be a venturi or other passive device operable at relatively low fluid pressure that draws coolant through suction at the venturi narrowing point and mixes the coolant with the fluid for injection. The injection device is operable with a known BWR design, where the device is attached to a steam connection to the main steam line of the reactor, a coolant connection drawing from suction lines to a suppression cool or condensate tank, and an outlet connection injecting into the main feedwater lines. In a BWR, the injection device is operable without electricity and at a wide range of pressures, even less than 50 pounds per square inch, to maintain coolant levels in the reactor. | 09-26-2013 |
| 20130266111 | STEAM GENERATOR FLOW BY-PASS SYSTEM - A nuclear reactor module includes a reactor vessel and a reactor housing mounted inside the reactor vessel, wherein the reactor housing comprises a shroud and a riser located above the shroud. The nuclear reactor module further includes a heat exchanger proximately located about the riser, and a reactor core located in the shroud. A steam generator by-pass system is configured to provide an auxiliary flow path of primary coolant to the reactor core to augment a primary flow path of the primary coolant out of the riser and into the shroud, wherein the auxiliary flow path of primary coolant exits the reactor housing without passing by the heat exchanger. | 10-10-2013 |
| 20130272473 | AUXILIARY CONDENSER SYSTEM FOR DECAY HEAT REMOVAL IN A NUCLEAR REACTOR - A nuclear reactor includes an internal steam generator and a nuclear core disposed in a containment structure. A condenser is disposed outside the containment structure, and includes a condenser inlet line tapping off a steam line connected to the steam generator outside the containment structure, and a condensate injection line conveying condensate from the condenser to the integral steam generator. Isolation valves are located outside the containment structure on a feedwater line, the steam line, and the condensate injection line. The valves have an operating configuration in which the isolation valves on the feedwater and steam lines are open and the isolation valve on the condensate injection line is closed, and a heat removal configuration in which the isolation valves on the feedwater and steam lines are closed and the isolation valve on the condensate injection line is open. | 10-17-2013 |
| 20130301781 | MODIFIED DRY ICE HEAT EXCHANGER FOR HEAT REMOVAL OF PORTABLE REACTORS - A novel heat exchanger (FIG. | 11-14-2013 |
| 20130301782 | DEFENSE IN DEPTH SAFETY PARADIGM FOR NUCLEAR REACTOR - A nuclear reactor includes a nuclear reactor core disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure. A containment structure contains the nuclear reactor. A reactor coolant inventory and purification system (RCI) is connected with the pressure vessel by make-up and letdown lines. The RCI includes a high pressure heat exchanger configured to operate responsive to a safety event at the operating pressure to remove heat from the primary coolant water in the pressure vessel. An auxiliary condenser located outside containment also removes heat. The RCI also includes a pump configured to inject make up water into the pressure vessel via the make-up line against the operating pressure. An emergency core cooling system (ECC) operates to depressurize the nuclear reactor only if the RCI and auxiliary condenser are unable to manage the safety event. | 11-14-2013 |
| 20130308737 | MECHANICAL CONNECTIONS AND METHODS - A mechanical connection between adjacent components of a system may include a first component of the system, a second component of the system, and a multiple degree-of-freedom connection between the first and second components. The multiple degree-of-freedom connection may have at least four degrees of freedom. A method for establishing a mechanical connection between adjacent components of a system may include disposing a first component of the system adjacent to a second component of the system, and connecting the first component to the second component using a multiple degree-of-freedom connection. The multiple degree-of-freedom connection may have at least four degrees of freedom. | 11-21-2013 |
| 20130336440 | COMBINED CORE MAKEUP TANK AND HEAT REMOVAL SYSTEM FOR A SMALL MODULAR PRESSURIZED WATER REACTOR - A combined makeup tank and passive residual heat removal system that places a tube and shell heat exchanger within the core makeup tank. An intake to the tube side of the heat exchanger is connected to the hot leg of the reactor core and the outlet of the tube side is connected to the cold leg of the reactor core. The shell side of the heat exchanger is connected to a separate heat sink through a second heat exchanger. | 12-19-2013 |
| 20130336441 | SMALL MODULAR REACTOR SAFETY SYSTEMS - An integral pressurized water reactor that combines all of the components typically associated with a nuclear steam supply system, such as the steam generator, reactor coolant pumps, pressurizer and the reactor, into a single reactor pressure vessel. The reactor pressure vessel is itself enclosed in a containment pressure vessel that also houses a number of safety systems, such as the core make-up tanks, the primary side of residual heat removal heat exchangers, an automatic depressurization system and a recirculation system that enables continuous core cooling through natural circulation over an extended period of time. Actuation of the passive systems is done by single actuation of valves, powered from redundant batteries. | 12-19-2013 |
| 20140003567 | NUCLEAR POWER PLANT AND PASSIVE CONTAINMENT COOLING SYSTEM | 01-02-2014 |
| 20140016733 | PASSIVE SAFETY INJECTION SYSTEM USING SAFETY INJECTION TANK - A passive safety injection system includes a containment, a reactor installed in the containment, safety injection tanks installed in the containment, a safety injection line between the reactor or a reactor coolant system and each of the safety injection tanks to guide water, which is stored in the safety injection tank, into the reactor when a water level in the reactor is reduced due to a loss of coolant accident, and a pressure balance line between the reactor or the reactor coolant system and the safety injection tank to guide high-temperature steam from the reactor into the safety injection tank upon the loss of coolant accident. The safety injection line has an orifice and a check valve thereon, and the pressure balance line has an orifice and isolation valves thereon. The water in the safety injection tank stably flows into the reactor for many hours. | 01-16-2014 |
| 20140016734 | PASSIVE SAFETY SYSTEM OF INTEGRAL REACTOR - A passive safety system includes a containment, a reactor in the containment, a plurality of safety injection tanks connected with the reactor and having water and nitrogen gas to supply water thereof into the reactor through a safety injection line communicating to the first safety injection line upon a loss of coolant accident, a plurality of core makeup tanks connected with the reactor to supply water thereof into the reactor through a second safety injection line communicating to a safety injection line upon the loss of coolant accident, and a plurality of passive residual heat removal systems to remove residual heat from the reactor upon the loss of coolant accident or a non-loss of coolant accident. The water in each of the safety injection tank is stably supplied to the reactor for many hours by a differential head resulting from gravity or gas pressure. | 01-16-2014 |
| 20140050292 | SEPARATE TYPE SAFETY INJECTION TANK AND INTEGRAL TYPE REACTOR HAVING THE SAME - A separate type safety injection tank comprises: a coolant injection unit connected to a reactor coolant system by a safety injection pipe such that coolant stored therein is injected into the reactor coolant system by a pressure difference from the reactor coolant system when a loss-of-coolant-accident (LOCA) occurs; a gas injection unit connected to the coolant injection unit, and configured to pressurize the coolant injected into the reactor coolant system, by introducing gas stored therein to an upper part of the coolant injection unit in the loss-of-coolant-accident; and a choking device disposed between the coolant injection unit and the gas injection unit, and configured to contract a flow cross-sectional area of the gas introduced to the coolant injection unit, and configured to maintain a flow velocity and a flow rate of the gas introduced to the coolant injection unit as a critical flow velocity and a critical flow rate when a pressure difference between the coolant injection unit and the gas injection unit is more than a critical value. | 02-20-2014 |
| 20140079172 | NUCLEAR REACTOR WITH DEVICE FOR INJECTING NANOPARTICLES IN THE EVENT OF AN ACCIDENT - A nuclear reactor is provided that includes a core with nuclear fuel assemblies; a circuit for cooling the core in which circulates a fluid coolant; and a device provided for injecting nanoparticles into the fluid coolant. The nanoparticles include first nanoparticles of a first type having a first form factor of less than two, and second nanoparticles of a second type different from the first type having a second form factor greater than two, the nanoparticles comprising between 10% and 90% by weight of the first nanoparticles and between 90% and 10% by weight of the second nanoparticles. | 03-20-2014 |
| 20140093025 | ARRANGEMENT AND METHOD FOR PROVIDING AN EMERGENCY SUPPLY TO A NUCLEAR INSTALLATION - The invention relates to a method and an arrangement for providing an emergency supply to a nuclear installation. The arrangement comprises a container ( | 04-03-2014 |
| 20140105348 | EMERGENCY AND BACK-UP COOLING OF NUCLEAR FUEL AND REACTORS - An embodiment uses liquid nitrogen, the densest and highly transportable form of nitrogen, and the cold nitrogen gas it produces when released from its container, for emergency cooling of fuel rods and nuclear reaction chambers. | 04-17-2014 |
| 20140112426 | Passive Residual Heat Removal System and Nuclear Power Plant Equipment - The invention includes a heat exchanger provided at a position higher than a primary containment vessel; a condensate storage tank disposed below the heat exchanger and above an upper end of a reactor core placed in a reactor pressure vessel; a non-condensate gas discharge line connected to an upper section of the condensate storage tank and to a suppression pool; a second condensate discharge line connected to a position below that section of the condensate storage tank to which a first end of the non-condensate gas discharge line is connected, and to the suppression pool; and a condensate return line connected to a position below that section of the condensate storage tank to which a first end of the second condensate discharge line is connected, and to a side portion of the reactor pressure vessel, the side portion being above the upper end of the core. | 04-24-2014 |
| 20140112427 | COMPLETELY PASSIVE COOLING SYSTEM FOR REACTOR CORE AFTER ACCIDENT OF LARGE-SCALE PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT - A passive cooling system for a reactor core of a large-scale pressurized water reactor nuclear power plant includes a shield building having an outer wall and a through air inlet arranged on an upper part of the outer wall, a water tank arranged at an upper part of the shield building, a cooling water distribution plate arranged above a top of a containment within the shield building, a spray pipe arranged at an inside of the top of the shield building and having a water inlet end and a water outlet end, wherein the water inlet end is connected to a bottom of the water tank and the water outlet end is extended to be above the cooling water distribution plate, and an air deflector arranged between the shield building and the containment and having an upper end connected to an inside of the top of the shield building. | 04-24-2014 |
| 20140205051 | PASSIVE SYSTEM FOR COOLING THE CORE OF A NUCLEAR REACTOR - A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days. | 07-24-2014 |
| 20140219409 | MULTI STAGE SAFETY INJECTION DEVICE AND PASSIVE SAFETY INJECTION SYSTEM HAVING THE SAME - The present disclosure may disclose a multi stage safety injection device, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance between the reactor vessel and the safety injection tank, and a set of safety injection lines connected to the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and connected to the safety injection tank with different heights to reduce a flow rate of coolant injected into the reactor vessel step by step according to the water level reduction of the safety injection tank in order to inject coolant to the reactor vessel at multi stages. | 08-07-2014 |
| 20140270044 | REFUELING WATER STORAGE TANK (RWST) WITH TAILORED PASSIVE EMERGENCY CORE COOLING (ECC) FLOW - A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe. | 09-18-2014 |
| 20140321594 | SUBMERGED ENERGY PRODUCTION MODULE - The module according to the invention includes means in the form of an elongated cylindrical box ( | 10-30-2014 |
| 20140328445 | ELECTRICITY PRODUCTION MODULE - The module according to the invention includes means in the form of an elongated cylindrical box ( | 11-06-2014 |
| 20140334590 | COOLING SYSTEM OF EMERGENCY COOLING TANK AND NUCLEAR POWER PLANT HAVING THE SAME - The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same. The emergency cooling tank cooling system includes an emergency cooling tank configured to store cooling water therein, the cooling water receiving heat, transferred from a nuclear reactor or a containment, when an accident occurs in the nuclear reactor, a heat exchanging device installed to be exposed to an outside of the emergency cooling tank to operate in air, and configured to externally emit heat by way of a heat exchange between fluid in the emergency cooling tank and the air such that the operation of the emergency cooling tank is continued even without refilling the cooling water, and an opening and closing unit installed at an upper portion of the emergency cooling tank to be located higher than a water level of the cooling water, and configured to be open by a flow of the fluid generated by an evaporation of the cooling water, the flow being formed due to a pressure difference from external air at pressure higher than a preset pressure, such that some of the fluid is externally emitted when a heat load exceeding a cooling capacity of the emergency cooling tank is transferred. | 11-13-2014 |
| 20140334591 | PASSIVE CONTAINMENT SPRAY SYSTEM - Provided is a passive containment spray system including: a spray coolant storage unit that communicates with a containment accommodating a reactor vessel and maintains equilibrium of pressure between the spray coolant storage unit and the containment; a spray pipe that is installed within the containment in such a manner that when an accident occurs, a coolant supplied from the spray coolant storage unit is sprayed into the containment through the spray pipe due to an increase in pressure within the containment; and a connection pipe one end of which is inserted into the spray coolant storage unit in such a manner as to provide a flow path along which the coolant flows and the other end of which is connected to the spray pipe in such a manner that the coolant is passively supplied to the spray pipe through the connection pipe therein. | 11-13-2014 |
| 20140376679 | COOLING SYSTEM OF NUCLEAR REACTOR CONTAINMENT STRUCTURE - A nuclear power plant includes a nuclear reactor containment structure housing a nuclear reactor, a pressure vessel containing condensed water therein and having a receiving space located lower than a bottom of the containment structure, a release pipe connecting the containment structure to the pressure vessel such that water vapor and fission products generated in the containment structure in the event of an accident is capable of flowing into the pressure vessel, and a recovery pipe connecting the pressure vessel to the containment structure such that the condensed water received in the pressure vessel is capable of flowing into the containment structure. When a level of the condensed water received in the pressure vessel is higher than a water level in the containment structure, the condensed water flows from the pressure vessel toward the containment structure by a water head difference. | 12-25-2014 |
| 20150043701 | SYSTEMS FOR DEBRIS MITIGATION IN NUCLEAR REACTOR SAFETY SYSTEMS - Filtering systems and methods remove debris from coolant in a nuclear reactor setting. One or more filters are installed outside coolant reservoirs specifically where coolant will flow toward the reservoir, such as during a transient or other coolant leak event. Useable filters permit coolant through-flow while catching, straining, diverting, or otherwise removing debris from the coolant without significant interference with the coolant flow. | 02-12-2015 |
| 20150131769 | NUCLEAR POWER PLANT, SAFETY SYSTEM WITH FUSE ELEMENT AND GRAVITY ELEVATOR - The present invention relates to a nuclear power plant and safety system with fuse element and gravity elevator, the buildings of the power plant subjected to contamination being buried below sea level and under borated water basins, and having a safety system free of electrical and electronic components to act in the event of possible accidents comprising, among others, means for flooding the buildings of the power plant with thermal fuses and gravity elevators for operator evacuation in the event of an emergency. | 05-14-2015 |
| 20150131770 | Emergency Core Cooling System and Emergency Core Cooling Method for Fail-Safe Water-Cooled Reactor System - An emergency core cooling system and method for a fail-safe water-cooled reactor is disclosed, which completely remove decay heat generated from a core in safety without the use of an active component (i.e., pump). The exemplary embodiments include a reactor vessel using water as a coolant and a moderator, and receiving therein a reactor core on which nuclear fission occurs; a containment surrounding the entire reactor system including the reactor vessel and condensing a vapor discharged from the reactor vessel when emergency core cooling is performed; a reactor cavity which surrounds the reactor vessel and in which water condensed in the containment is collected due to gravity; a first cavity pipe provided to pass through the reactor vessel; and a cavity valve provided on the cavity pipe to open the first cavity pipe when emergency core cooling is performed and discharge the vapor generated from the reactor vessel. | 05-14-2015 |
| 20150357061 | NUCLEAR REACTOR COOLANT PUMP WITH HIGH DENSITY COMPOSITE FLYWHEEL - A nuclear reactor coolant pump (RCP) comprises a stator and a rotating assembly including a rotor, an impeller, and a flywheel configured to rotate about an axis of rotation in response to the stator being electrically energized. The flywheel comprises a first material (such as stainless steel) and has a plurality of mutually parallel tubular openings filled with a second material that is denser than the first material (such as tungsten or tungsten alloy). In some embodiments the mutually parallel tubular openings are cylindrical openings, and are filled with the second material comprising cylindrical rods. In a nuclear reactor including a reactor pressure vessel and a nuclear reactor core comprising fissile | 12-10-2015 |
| 20150380115 | LIQUID NITROGEN EMERGENCY COOLING SYSTEM FOR NUCLEAR POWER PLANTS - A reactor cooling system for cooling a nuclear reactor using nitrogen comprising a refrigeration unit for cooling and compressing nitrogen gas into liquid nitrogen, a liquids storage tank to store liquid nitrogen, the tank in fluid communication with the refrigeration unit, a heat exchanger drop system in fluid communication with the liquids storage tank, adjacent to the nuclear reactor, wherein the nitrogen absorbs heat by becoming gaseous, a tank for receiving and holding nitrogen gas in fluid communication with the heat exchanger and in fluid communication with the refrigeration unit, and where the system is a closed-loop drop system. | 12-31-2015 |
| 20160019989 | Method of Cooling Nuclear Reactor and Nuclear Reactor Including Polyhedral Boron Hydride or Carborane Anions - A method of cooling a nuclear reactor core is disclosed. The method includes contacting the nuclear reactor core with an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions. Nuclear reactors are also disclosed. The nuclear reactor has a neutron moderator that is an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions, or the nuclear reactor has an emergency core cooling system including a vessel containing a volume of an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions. The nuclear reactor can also have both an aqueous solution comprising at least one of polyhedral boron hydride anions or carborane anions as a neutron moderator and an emergency core cooling system that includes an aqueous solution comprising at least one of polyhedral boron hydride an ions or carborane anions. | 01-21-2016 |
| 20160027535 | INTEGRAL ISOLATION VALVE SYSTEMS AND METHODS OF OPERATING SAME FOR LOSS OF COOLANT ACCIDENT (LOCA) PROTECTION - A nuclear reactor includes a nuclear reactor core comprising fissile material disposed in a reactor pressure vessel having vessel penetrations that exclusively carry flow into the nuclear reactor and at least one vessel penetration that carries flow out of the nuclear reactor. An integral isolation valve (IIV) system includes passive IIVs each comprising a check valve built into a forged flange and not including an actuator, and one or more active IIVs each comprising an active valve built into a forged flange and including an actuator. Each vessel penetration exclusively carrying flow into the nuclear reactor is protected by a passive IIV whose forged flange is directly connected to the vessel penetration. Each vessel penetration carrying flow out of the nuclear reactor is protected by an active IIV whose forged flange is directly connected to the vessel penetration. Each active valve may be a normally closed valve. | 01-28-2016 |
| 20160055924 | Boiling Water Type Nuclear Power Plant - To more reliably supply cooling water to a reactor pressure vessel and a reactor containment vessel using a back-up building if a severe accident should occur, a boiling water type nuclear power plant includes a nuclear reactor building including a reactor containment vessel, and an external building, which is installed independently outside the nuclear reactor building and which has an anti-hazard property. The external building has a power source and an operating panel independent of the nuclear reactor building. The boiling water type nuclear power plant includes a water injection pump installed inside the external building, an alternative water injection pipe performing water injection at least on a reactor pressure vessel or the reactor containment vessel in the nuclear reactor building from the water injection pump, and a valve connected to the alternative water injection pipe, making it possible to perform alternative water injection if a severe accident occurs. | 02-25-2016 |
| 20160099084 | METHOD OF PLATINUM INJECTION INTO A NUCLEAR REACTOR - A method of injecting platinum into a Boiling Water Reactor is provided. The Boiling Water Reactor includes a reactor core including a plurality of fuel rods having a zirconium alloy cladding. The method includes injecting a first platinate compound and a second platinate compound into a nuclear reactor. The first platinate compound is non-alkalizing and the second platinate compound includes an alkalizing element. The first platinate compound and the second platinate compound are injected such that the second platinate compound injected does not exceed a predetermined threshold or such that a value related to an alkalizing element of the second platinate compound does not exceed a predetermined threshold. | 04-07-2016 |
| 20160118147 | Passive System for Cooling the Core of a Nuclear Reactor - A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days. | 04-28-2016 |
| 20160141056 | Passive Nuclear Reactor Emergency Cooling System Using Compressed Gas Energy and Coolant Storage Outside Nuclear Plant - A passive safety system for a nuclear power plant ( | 05-19-2016 |
