| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376298000 | Auxiliary heat removal structure | 52 |
| 20090116608 | NATURAL CIRCULATION TYPE BOILING WATER REACTOR - A natural-circulation type boiling water reactor according to the present invention includes a plurality of divided chimneys provided above a reactor core and a number of fuel assemblies are charged in the reactor core. The natural-circulation type boiling water reactor is provided with a pressure equalization structure arranged on rectangular-columnar lattice plates of the divided chimneys at an outlet of the reactor core for equalizing pressures in divided chimney portions so as to equalize the pressures of the divided chimneys with the pressure equalization structure. | 05-07-2009 |
| 20110200156 | Method, system, and apparatus for the thermal storage of nuclear reactor generated energy - A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system. | 08-18-2011 |
| 20120236980 | NUCLEAR POWER STATION - A nuclear power station has a containment in which a reactor core is accommodated. According to the invention, an external cooling system for cooling the containment in the event of an accident is associated with the containment. The cooling system in particular has a coolant reservoir that is configured as a lake or is lake-like, and in which the containment is in contact with a coolant or may be brought into contact with a coolant, in particular a liquid coolant, in the event of an accident. | 09-20-2012 |
| 20120250813 | SELF-CONTAINED EMERGENCY SPENT NUCLEAR FUEL POOL COOLING SYSTEM - An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required. | 10-04-2012 |
| 20120307956 | NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT - A nuclear reactor system that, in one embodiment, utilizes natural circulation (i.e., thermosiphon) to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heal exchange sub-system is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heal exchange sub-system that is used to vaporize a secondary coolant. In another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground. | 12-06-2012 |
| 20130064341 | PASSIVE AUXILIARY CONDENSING APPARATUS OF NUCLEAR POWER PLANT - A passive auxiliary condensing apparatus of a nuclear power plant includes a steam generation unit configured to heat a water supplied thereto into a steam by a heat produced when operating a nuclear reactor, a water cooled heat exchange unit connected to the steam generation unit and configured to store a cooling water therein to condense the steam provided from the steam generation unit, and a steam-water separation tank including a first side connected to the water cooled heat exchange unit and a second side connected to the steam generation unit, wherein a mixture of a water and a steam provided from the water cooled heat exchange unit is separated into the water and the steam to provide only the water to the steam generation unit. | 03-14-2013 |
| 20130064342 | PASSIVE COOLING SYSTEM OF NUCLEAR POWER PLANT - A passive cooling system of a nuclear power plant includes a cooling water storage tank configured to store a cooling water therein, a steam generation unit to which the cooling water is supplied from the cooling water storage tank connected thereto, the supplied cooling water being heated to generate a steam, a water cooling heat exchange unit connected to the steam generation unit and provided within the cooling water storage tank, and an air cooling heat exchange unit connected to the steam generation unit and provided outside the cooling water storage tank. | 03-14-2013 |
| 20130156143 | EMERGENCY CORE COOLING SYSTEM (ECCS) FOR NUCLEAR REACTOR EMPLOYING CLOSED HEAT TRANSFER PATHWAYS - A containment structure contains an interior volume, and a nuclear reactor is disposed in the interior volume. An ultimate heat sink pool is disposed outside of the containment structure. A condenser includes a plurality of closed-path heat pipes or closed-path thermosiphons having first ends and opposite second ends. The closed-path heat pipes or closed-path thermosiphons are embedded in the containment structure with the first ends protruding into the interior volume and the second ends protruding outside of the containment structure. | 06-20-2013 |
| 20130156144 | METHOD AND APPARATUS FOR AN ALTERNATIVE REMOTE SPENT FUEL POOL COOLING SYSTEM FOR LIGHT WATER REACTORS - A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency. | 06-20-2013 |
| 20130202075 | WATER-SPRAY RESIDUAL HEAT REMOVAL SYSTEM FOR NUCLEAR POWER PLANT - A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct. | 08-08-2013 |
| 20140072088 | METHOD AND SYSTEM FOR EXTERNAL ALTERNATE SUPPRESSION POOL COOLING FOR A BWR - A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink fluidly coupled to cooling coils surrounding the suppression pool. Cool water may be pumped through the cooling coils without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system may also be operated and controlled from a remote location to protect the safety of plant personnel. | 03-13-2014 |
| 20140072089 | METHOD AND SYSTEM FOR AN ALTERNATIVE BWR CONTAINMENT HEAT REMOVAL SYSTEM - A method and apparatus for an alternative cooling system used to cool the suppression pool of a Boiling Water Reactor (BWR) nuclear reactor. The cooling system includes a cooling coil in an isolation condenser located at an elevation that is above the suppression pool. The isolation condenser is connected to the suppression pool via inlet and outlet pipes. The system may provide a natural convection flow of fluids between the suppression pool and the cooling coils to passively cool fluid from the suppression pool without requiring external electrical power. | 03-13-2014 |
| 20140072090 | METHOD AND SYSTEM FOR AN ALTERNATE RPV ENERGY REMOVAL PATH - A method and system for an alternate energy removal path for a reactor pressure vessel (RPV) of a light water reactor. A pair of manually operated containment isolation valves, one located inside and one located outside of primary containment, are used to open and close a steam extraction line that is fluidly coupled between the RPV and a heat sink. The heat sink is located outside of primary containment. A source of external electrical power is not required to operate the system or perform the method. | 03-13-2014 |
| 20140192947 | SUBMERGED ELECTRICITY PRODUCTION MODULE - The underwater electricity production module according to the invention includes means in the form of an elongated cylindrical box ( | 07-10-2014 |
| 20140294134 | SUBMERGED ELECTRICITY PRODUCTION MODULE - The underwater electricity production module according to the invention, of the type including means in the form of an elongated cylindrical box ( | 10-02-2014 |
| 20140321596 | PASSIVE REACTOR COOLING SYSTEM - A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger. | 10-30-2014 |
| 20140321597 | LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM - A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink. | 10-30-2014 |
| 20150146838 | NUCLEAR REACTOR HAVING PLATE OR MICRO-CHANNEL HEAT EXCHANGERS INTEGRATED IN THE VESSEL - A nuclear reactor is provided that includes a vessel; a core provided in the vessel; at least one plate heat exchanger provided in the vessel, with at least one duct for supplying a secondary fluid to the heat exchanger and a duct for discharging the secondary fluid from the heat exchanger, the discharge duct extending through the vessel. The nuclear reactor comprises a device for attaching the heat exchanger to an area of the vessel through which the discharge duct extends. | 05-28-2015 |
| 20150294745 | Nuclear Reactor with Liquid Metal Coolant - A nuclear reactor with a liquid metal coolant includes a housing having a separating shell disposed therein. In the annular space between the housing and the separating shell are disposed at least one steam generator and at least one pump. Inside the separating shell there is an active region, above which a heat collector is disposed in communication with the vertically central portion of the steam generator in order to separate a stream of liquid metal coolant into ascending and descending flows, or the heat collector is in communication with the upper portion of the steam generator in order to create a counter-flow heat exchange regime. Below the reactor head is an upper horizontal cold collector with an unfilled level of coolant, and below the steam generator is a lower accumulating collector in communication with the upper cold collector. | 10-15-2015 |
| 20150357057 | NUCLEAR REACTOR CAVITY FLOOR PASSIVE HEAT REMOVAL SYSTEM - A nuclear reactor includes a reactor core disposed in a reactor pressure vessel. A radiological containment contains the nuclear reactor and includes a concrete floor located underneath the nuclear reactor. An ex vessel corium retention system includes flow channels embedded in the concrete floor located underneath the nuclear reactor, an inlet in fluid communication with first ends of the flow channels, and an outlet in fluid communication with second ends of the flow channels. In some embodiments the inlet is in fluid communication with the interior of the radiological containment at a first elevation and the outlet is in fluid communication with the interior of the radiological containment at a second elevation higher than the first elevation. The radiological containment may include a reactor cavity containing a lower portion of the pressure vessel, wherein the concrete floor located underneath the nuclear reactor is the reactor cavity floor. | 12-10-2015 |
| 20160203880 | AIR COOLER, INTERCOOLER AND NUCLEAR FACILITY | 07-14-2016 |
| 376299000 | Decay heat removal | 31 |
| 20080219397 | Decay Heat Removal System for Liquid Metal Reactor - A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant. | 09-11-2008 |
| 20090129531 | SUBMERGED CONTAINMENT VESSEL FOR A NUCLEAR REACTOR - A power module assembly includes a reactor core immersed in a coolant and a reactor vessel housing the coolant and the reactor core. An internal dry containment vessel submerged in liquid substantially surrounds the reactor vessel in a gaseous environment. During an over-pressurization event the reactor vessel is configured to release the coolant into the containment vessel and remove a decay heat of the reactor core through condensation of the coolant on an inner surface of the containment vessel. | 05-21-2009 |
| 20090245453 | DECAY HEAT REMOVAL SYSTEM COMPRISING HEAT PIPE HEAT EXCHANGER - Disclosed herein is a decay heat removal system, including: a decay heat exchanger that absorbs decay heat generated by a nuclear reactor; a heat pipe heat exchanger that receives the decay heat from the decay heat exchanger through a sodium loop for heat removal and then discharges the decay heat to the outside; and a sodium-air heat exchanger that is connected to the heat pipe heat exchanger through the sodium loop and discharges the decay heat transferred thereto through the sodium loop to the outside. According to the decay heat removal system, a heat removal capability can be realized by the heat pipe heat exchanger at such a high temperature at which the safety of a nuclear reactor is under threat, and a cooling effect can be obtained through the sodium-air heat exchanger at a temperature lower than that temperature. | 10-01-2009 |
| 20100177860 | FULLY PASSIVE DECAY HEAT REMOVAL SYSTEM FOR SODIUM-COOLED FAST REACTORS THAT UTILIZES PARTIALLY IMMERSED DECAY HEAT EXCHANGER - Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes. | 07-15-2010 |
| 20100226471 | SYSTEM FOR EVACUATING THE RESIDUAL HEAT FROM A LIQUID METAL OR MOLTEN SALTS COOLED NUCLEAR REACTOR - A system for evacuating the residual heat from a nuclear reactor cooled with liquid metal or molten salts has two types of heat exchangers immersed in the primary fluid of the reactor: heat exchangers with higher power density, which use boiling water as secondary cooling fluid and are particularly suitable for evacuating the residual heat in the first days after turning-off of the reactor; and heat exchangers operating with atmospheric air or with water and suitable for evacuating the residual heat for indefinite periods of time. Both types of heat exchangers present a bundle of heat-exchange elements, shaped in such a way that the secondary fluid circulating in each element is separated from the primary fluid of the reactor by a double wall of the element, which delimits a gap introduced in which is a pressurized inert gas having the function of continuous monitoring of the integrity of the heat exchanger and of thermal resistance calibrated for preventing solidification of the primary fluid of the reactor in the heat exchanger. | 09-09-2010 |
| 20100260303 | Method and system for the thermoelectric conversion of nuclear reactor generated heat - A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system. | 10-14-2010 |
| 20100260304 | Method, system, and apparatus for the thermoelectric conversion of gas cooled nuclear reactor generated heat - A method, system, and apparatus for the thermoelectric conversion of nuclear reactor generated heat including thermoelectrically converting gas cooled nuclear reactor generated heat to electrical energy and supplying the electrical energy to an operation system of the nuclear reactor system. | 10-14-2010 |
| 20100260305 | Method, system, and apparatus for the thermoelectric conversion of gas cooled nuclear reactor generated heat - A method, system, and apparatus for the thermoelectric conversion of nuclear reactor generated heat including thermoelectrically converting gas cooled nuclear reactor generated heat to electrical energy and supplying the electrical energy to an operation system of the nuclear reactor system. | 10-14-2010 |
| 20100260306 | Method and system for the thermoelectric conversion of nuclear reactor generated heat - A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system. | 10-14-2010 |
| 20100260307 | Method and system for the thermoelectric conversion of nuclear reactor generated heat - A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system. | 10-14-2010 |
| 20100260308 | Method, system, and apparatus for selectively transferring thermoelectrically generated electric power to nuclear reactor operation systems - A method, system, and apparatus for the selective transfer of thermoelectrically generated electric power to operation systems of a nuclear reactor system including thermoelectrically converting nuclear reactor generated heat to electrical energy and selectively transferring the electrical energy to at least one operation system of the nuclear reactor system. | 10-14-2010 |
| 20100260309 | Method, System, and apparatus for selectively transferring thermoelectrically generated electric power to nuclear reactor operation systems - A method, system, and apparatus for the selective transfer of thermoelectrically generated electric power to operation systems of a nuclear reactor system including thermoelectrically converting nuclear reactor generated heat to electrical energy and selectively transferring the electrical energy to at least one operation system of the nuclear reactor system. | 10-14-2010 |
| 20100290576 | BOILING WATER REACTOR - A boiling water reactor has a reactor pressure vessel and a through piping. The reactor pressure vessel includes a main body trunk and an openable upper lid covering an upper open end of the main body trunk from above. The through piping penetrates lateral side of the main body trunk and has an opening section at a same level with or higher than the upper open end of the main body trunk in the reactor pressure vessel. The through piping may be connected to the sump arranged outside the reactor pressure vessel in the dry well. The through piping may be further connected to the suppression pool in the wet well and/or to the water level gauge in the dry well. | 11-18-2010 |
| 20120328068 | DECAY HEAT CONVERSION TO ELECTRICITY AND RELATED METHODS - Various embodiments of a decay heat conversion to electricity system and related methods are disclosed. According to one exemplary embodiment, a decay heat conversion to electricity system may include a spent fuel rack configured to pressurize spent fuel bundles to obtain superheated vapor to drive a turbine-driven pump and fast alternator all submerged with the spent fuel rack and positioned at the bottom of the spent fuel pool for conversion of electricity distributed outside of the spent fuel pool via cables without impairing spent fuel pool operations. | 12-27-2012 |
| 20130044851 | BACKUP NUCLEAR REACTOR AUXILIARY POWER USING DECAY HEAT - A nuclear plant auxiliary backup power system that uses decay heat following a plant shutdown to produce electrical power through a dedicated steam turbine/generator set. The decay heat produces a hot operating gaseous fluid which is used as a backup to run an appropriately sized turbine that powers an electrical generator. The turbine is configured to utilize a portion of the existing nuclear plant secondary system and exhausts the turbine exhaust to the ambient atmosphere. The system functions to both remove reactor decay heat and provide electrical power for plant systems to enable an orderly shutdown in the event traditional sources of electric power are unavailable. | 02-21-2013 |
| 20130121454 | SEMI-PORTABLE EMERGENCY COOLING SYSTEM FOR REMOVING DECAY HEAT FROM A NUCLEAR REACTOR - An emergency temporary spent fuel pool cooling system for a nuclear power generating facility that has a permanently installed primary loop within the nuclear containment and a mobile temporary secondary loop. The secondary loop is housed in transport vehicles that can be stored off site and is connectable in heat exchange relationship with the primary loop through quick disconnect couplings that are accessible on the outside of the reactor containment. The transport vehicles also include self-contained power and compressed air sources for powering and controlling the entire emergency cooling system. The system also has a make-up water injection capability for refueling the spent fuel pool and secondary loop. | 05-16-2013 |
| 20130156145 | METHOD AND APPARATUS FOR AN ALTERNATIVE SUPPRESSION POOL COOLING FOR BOILING WATER REACTORS - A method and apparatus for providing an alternative cooling system for the suppression pool of a Boiling Water Reactor (BWR) nuclear reactor. The cooling system is operated to cool the suppression pool in the event of a plant accident when normal plant electricity is not available for the conventional residual heat removal system and pumps. The cooling system may also be used to supplement the cooling of the suppression pool via the residual heat removal system. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency. | 06-20-2013 |
| 20130272474 | PASSIVE CONTAINMENT AIR COOLING FOR NUCLEAR POWER PLANTS - An enhanced passive containment air cooling system for a nuclear power plant that increases the heat transfer surface on the exterior of the nuclear plant's containment vessel. The increased surface area is created by forming a tortuous path in or on at least a substantial part of the exterior surface of the containment vessel over which a cooling fluid can flow and follow the tortuous path. The tortuous path is formed from a series of indentations and protrusions in or on the exterior surface that form a circuitous path for the cooling fluid. | 10-17-2013 |
| 20130272475 | PASSIVE CONTAINMENT AIR COOLING FOR NUCLEAR POWER PLANTS - A passive containment air cooling system for a nuclear power plant that enhances air flow over a metal containment that houses the reactor system to improve heat transfer out of the containment. The heat transfer is improved by employing swirl vanes to mix the air as it rises over the walls of the containment due to natural circulation and a vortex engine proximate an exit along the cooling air path to increase the quantity of air drawn along the containment. | 10-17-2013 |
| 20130308738 | HEAT TRANSFER SYSTEMS AND METHODS FOR NUCLEAR PLANTS - A heat transfer system for a nuclear plant may include a piping system that includes first and second connectors, heat exchanger, pump, and power source. The heat transfer system may not be connected to the plant during normal power operations. The power source may be independent of a normal electrical power distribution system for the plant and may be configured to power the pump. The piping system may be configured to connect the heat exchanger and pump. The connectors may be configured to connect the heat transfer system to a fluid system of the plant. When the connectors connect the heat transfer system to the fluid system, the heat transfer system may be configured to receive fluid from the fluid system of the plant via the first connector, to pump the fluid through the heat exchanger, and to return the fluid to the fluid system via the second connector. | 11-21-2013 |
| 20130343504 | HEAT EXCHANGER FOR PASSIVE RESIDUAL HEAT REMOVAL SYSTEM - Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved. | 12-26-2013 |
| 20140029711 | PASSIVE POWER PRODUCTION DURING A NUCLEAR STATION BLACKOUT - Apparatus for passively generating electric power during a nuclear power station blackout by utilizing the temperature difference between the hot inlet of a residual heat removal circuit and the surrounding containment environment. A heat engine, such as a thermoelectric generator, a Sterling Cycle Engine or Rankine Cycle Engine, is coupled in heat exchange relationship with an uninsulated portion of the inlet to a passive residual heat removal heat exchanger and/or passive residual heat removal heat exchanger channel head to generate the power required to operate essential equipment needed to maintain the nuclear power station in a safe condition during a loss of normal onsite and offsite power. | 01-30-2014 |
| 20140219411 | ALTERNATE PASSIVE SPENT FUEL POOL COOLING SYSTEMS AND METHODS - The present invention relates to passive cooling systems and methods for cooling a spent fuel pool in a nuclear power plant in the absence of onsite and offsite power, e.g., in a station blackout event. The systems include a gap formed along the periphery of the spent fuel pool, a heat sink, one or more thermal conductive members, a water supply system for delivering water to at least partially fill the gap and conduct heat generated from the spent fuel pool through the gap to at least one thermal conductive member for transporting heat to the heat sink, and a thermal switch mechanism for activating and deactivating the water supply system. | 08-07-2014 |
| 20140270045 | NUCLEAR REACTOR CORES COMPRISING A PLURALITY OF FUEL ELEMENTS, AND TO FUEL ELEMENTS FOR USE THEREIN - In a nuclear reactor core, each of a plurality of pressure tubes contains fuel elements spaced apart to permit coolant to flow through spaces between adjacent fuel elements. Each fuel element comprises fuel pellets in cladding, e.g., sapphire, having a melting temperature of at least 1900° C. and does not form significant hydrogen if exposed to high temperature steam. Each pressure tube has an internal insulator sleeve, e.g., fused silica, that has relatively low thermal conductivity over a range of normal operating temperatures and relatively high thermal radiation transmission at temperatures higher than said normal operating temperature range. When coolant is absent from said spaces, the insulator sleeve transmits to the pressure tube at least about 10%, but preferably more than about 40% of thermal radiation from the fuel for conduction through the pressure tube to the moderator and fuel temperature remains within safe limits after the reactor is shut down. | 09-18-2014 |
| 20140362968 | SYSTEM FOR REMOVING THE RESIDUAL POWER OF A PRESSURISED WATER NUCLEAR REACTOR - A system for removing the residual power of a pressurised water nuclear reactor, includes a reserve of water, a steam generator, wherein the primary water heated by the core either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and a condenser housed in the containment vessel. The condenser includes a recovery unit for recovering the condensed water and a condenser link to ensure the circulation of water in a closed circuit between the reserve and the condenser. The system further includes a device for circulating the secondary water between the steam generator and the condenser, the device being activated without an external supply of electrical energy, when an operating parameter characteristic of excessive heating of the primary water reaches a certain threshold, such that the primary water heated by the core and circulating in the steam generator vaporises the secondary water. | 12-11-2014 |
| 20150023461 | DECAY HEAT REMOVAL SYSTEM WITH HYBRID HEAT PIPE HAVING COOLANT AND NEUTRON ABSORBER FOR COOLING NUCLEAR POWER PLANT - Disclosed is a decay heat removal system for cooling the decay heat of a reactor core and the spent fuel. The decay heat removal system including: a first heat pipe which is placed in an upper plenum of the reactor vessel and arranged in upward and downward directions corresponding to a position of an insertion hole formed on a top of the nuclear fuel assemblies; a control rod drive mechanism which is connected to an upper portion of the first heat pipe and drives the first heat pipe to move up and down so that the first heat pipe can be selectively inserted in a control rod insertion hole of the reactor core arranged in the nuclear reactor vessel; and a second heat pipe which is coupled to and in close contact with a bottom surface of the reactor vessel and removes the decay heat generated in the reactor core. | 01-22-2015 |
| 20160019990 | COOLING SYSTEM FOR STORED NUCLEAR FUEL - A cooling system for cooling nuclear fuel stored in a pool that can prevent a lowering of water level resulting from evaporation is provided. The cooling system cools the nuclear fuels 3 stored in a bottom of the pool 2 filled with cooling water 4. The cooling water 4 comprises an upper layer formed in a water surface as side in which a density of the cooling water 4 is low, a lower layer formed in the bottom side of the pool 2 in which a density of the cooling water 4 is high, and an intermediate layer in which a density of the cooling water 4 is in between those of the cooling waters 4 in the upper layer and the lower layer. A lower end 5 | 01-21-2016 |
| 20160099085 | ENVIRONMENTALLY SUQUESTERED SPENT FUEL POOL - An environmentally sequestered nuclear spent fuel pool in one embodiment includes sidewalls and a base slab that confine a water impoundment. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A dual liner system enclosing the pool forms an impervious barrier providing redundant provisions for preventing leakage of contaminated pool water into the environment. An interstitial space is formed between the liners which may be maintained at sub-atmospheric pressures by a vacuum pump system that evacuates the space. By maintaining the pressure in the space at a negative pressure with corresponding boiling point less than the temperature of the pool water, any leakage through the inner-most liner into the interstitial space will vaporize and be extracted via the pump for signaling a potential leak in the liner system. | 04-07-2016 |
| 20160118148 | HEAT TRANSFER METHODS FOR NUCLEAR PLANTS - A method of transferring heat from a nuclear plant may include: connecting a heat transfer system to the nuclear plant; and using the heat transfer system to transfer heat from the nuclear plant. The heat transfer system may include: a piping system that includes first and second connectors; a heat exchanger; a pump; and a power source. The heat transfer system may not be connected to the nuclear plant during normal plant power operations. The power source may be independent of a normal electrical power distribution system for the nuclear plant. The power source may be configured to power the pump. The piping system may be configured to connect the heat exchanger and pump. The first and second connectors may be configured to connect the heat transfer system to a fluid system of the nuclear plant. | 04-28-2016 |
| 20160125963 | INTRINSICALLY SAFE NUCLEAR REACTOR - An improved nuclear fission reactor of the liquid metal cooled type including a core configuration allowing for only two operational states, “Power” or “Rest”. The flow of the primary cooling fluid suspends the core in the “Power” state, with sufficient flow to remove the heat to an intermediate heat exchanger during normal operation. This invention utilizes the force of gravity to shut down the reactor after any loss of coolant flow, either a controlled reactor shut down or a “LOCA” event, as the core is controlled via dispersion of fuel elements. Electromagnetic pumps incorporating automatic safety electrical cut-offs are employed to shutdown the primary cooling system to disassemble the core to the “Rest” configuration due to a loss of secondary coolant or loss of ultimate heat sink. This invention is a hybrid pool-loop pressurized high-temperature or unpressurized reactor unique in its use of a minimum number of components, utilizing no moving mechanical parts, no rotating seals, optimized piping, and no control rods. Thus defining an elegantly simple intrinsically safe nuclear reactor. | 05-05-2016 |
| 20160196886 | Reactor Cooling System | 07-07-2016 |
