| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376261000 | Fuel component | 55 |
| 20080267338 | Methods of editing fuel bundle groups - A method of fuel bundle consideration in a reactor. The method includes creating or editing bundle groups including fuel bundles. | 10-30-2008 |
| 20090080587 | Nuclear fission igniter - Illustrative embodiments provide nuclear fission igniters for nuclear fission reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, a nuclear fission igniter configured to ignite a nuclear fission deflagration wave in nuclear fission fuel material, a nuclear fission deflagration wave reactor with a nuclear fission igniter, a method of igniting a nuclear fission deflagration wave, and the like. | 03-26-2009 |
| 20090080588 | Nuclear fission igniter - Illustrative embodiments provide nuclear fission igniters for nuclear fission reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, a nuclear fission igniter configured to ignite a nuclear fission deflagration wave in nuclear fission fuel material, a nuclear fission deflagration wave reactor with a nuclear fission igniter, a method of igniting a nuclear fission deflagration wave, and the like. | 03-26-2009 |
| 20090252273 | Automated nuclear power reactor for long-term operation - 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. | 10-08-2009 |
| 20090257545 | REINFORCEMENT FOR A NUCLEAR FUEL ASSEMBLY - A tie rod for reinforcing a nuclear fuel assembly. The tie rod includes an outer, hollow tubular member that extends from above the top nozzle through the bottom nozzle of the fuel assembly and has an axially split lower tip with an enlarged end and an upper portion having a circumferential threaded region. An inner rod extends axially through the hollow of the outer tube and has a slightly enlarged tip which spreads the split tip of the outer tube to lock the split tip below the lower nozzle of the fuel assembly. A nut is turned down on the upper threaded portion of the outer hollow tube and staked in position to lock the tie rod in position. | 10-15-2009 |
| 20100232563 | APPARATUS AND METHOD FOR SUPPORTING FUEL ASSEMBLIES IN AN UNDERWATER ENVIRONMENT HAVING LATERAL ACCESS LOADING - A method of loading nuclear fuel assemblies into a fuel rack in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. In one embodiment, the method comprises submerging a nuclear fuel assembly having an axis and a horizontal cross-section in a pool; providing a fuel rack in the pool, the fuel rack comprising a body structure comprising at least one elongated cell, a top, a bottom, a first lateral side, at least one elongated slot in the first lateral side that forms a lateral passageway into the cell; positioning the fuel assembly laterally adjacent to the elongated slot of the fuel rack so that the axis of the fuel assembly is substantially aligned with the elongated slot; and translating the fuel assembly in a lateral direction through the elongated slot and into the cell. | 09-16-2010 |
| 20100246742 | SYSTEM FOR ASSEMBLING OR DISASSEMBLING A SEGMENTED ROD - An embodiment of the present invention takes the form of a system that allows for simultaneously assembling or disassembling multiple segmented nuclear fuel rods (hereinafter “segmented rods”). An embodiment of the present invention, may receive, secure, and move the segmented rods into a position that allows for performing the tasks of either assembly or disassembly, allowing for an operator to use a tool to complete the aforementioned tasks. | 09-30-2010 |
| 20100272224 | FUEL TRANSFER SYSTEM - A fuel transfer system is used for transporting spent fuel from a first room to a second room. The system includes a carriage configured for travel between the first room and the second room, and a boom assembly that extends and retracts between the first room and the second room, wherein the boom assembly facilitates travel of the carriage. The system also includes a hoist system positioned in the first room. The hoist system includes at least one boom cable interconnected with the boom assembly to extend and retract the boom assembly. The hoist system also includes at least one carriage cable interconnected with the carriage to move the carriage. | 10-28-2010 |
| 20110103537 | CHANNEL SEATING TOOL FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR SEATING CHANNEL ON THE ASSEMBLY - A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel. | 05-05-2011 |
| 20110216871 | Channel-Lifting Tool and Method - A lifting tool is used for lifting a channel on and off of a nuclear fuel bundle. The lifting tool includes a lifting bail and a leg assembly secured to the lifting bail. The leg assembly has an adjustable width, adjustable between a narrower pre-lifting position and a wider lifting position. The lifting legs are engageable with the channel clips in the lifting position. | 09-08-2011 |
| 20120039428 | METHOD FOR ALIGNING AND HANDLING FUEL RODS WITHIN A NUCLEAR FUEL BUNDLE - A method of aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle located in a spent fuel pool of a nuclear power plant. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The method includes insertion of a rod grapple tool into a top end of a fuel bundle and down to a desired location within the bundle. A guide pin retrieval tool inserts into a side of the fuel bundle to remove a guide pin from a distal end of a gripper of the rod grapple tool, allowing the guide pin retrieval tool to grip a part-length fuel rod within the fuel bundle. | 02-16-2012 |
| 20120201340 | System and Method for Integration of Wet and Dry Nuclear Fuel Storage - Systems and methods of loading and/or removing spent nuclear fuel from a spent nuclear fuel pool are disclosed. A spent fuel basket compatible with a dry storage and/or transport system is disposed in a spent nuclear fuel pool. At least one spent fuel assembly is loaded in one of a plurality of chambers associated with the spent fuel basket. The spent fuel basket is inserted into a spent fuel canister. The spent fuel canister is loaded into a transfer cask. The spent fuel canister is then transferred from the transfer cask to a storage cask or a transport cask, which can be sealed and stored on-site or in an off-site storage facility. | 08-09-2012 |
| 20130010913 | NUCLEAR FUEL ASSEMBLY POSITIONING SYSTEM HAVING BUILT-IN SOLENOID VALVE BOX - Provided is a nuclear fuel assembly positioning system having a built-in solenoid valve box in an apparatus for testing nuclear fuel used in an atomic power plant. A work table is installed at a predetermined position within an underwater fuel storage pool, and a solenoid valve box connected to two pneumatic hoses extending from the outside is integrally installed on an test table so as to drive the test table, so that only the two pneumatic hoses simplified as a gas supply hose and a gas discharge hose are connected with the test table, and thus the nuclear fuel assembly is accurately and rapidly positioned as to be able to conveniently perform testing without the structures around the hoses being interfered with when pneumatic motors are operated. | 01-10-2013 |
| 20130177124 | DEVICE FOR THE DRY HANDLING OF NUCLEAR FUEL ASSEMBLIES - A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask. | 07-11-2013 |
| 20130272470 | Radial Neutron Reflector - A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners. | 10-17-2013 |
| 20140153686 | Gripping and Locking/Unlocking System, and Application to the Handling of Nuclear Materials Specimen Holders - A system for gripping an inner tube and locking/unlocking it into and from an outer tube concentric with the inner tube. The system according to the invention is provided with one or more catching devices which allow both sealed locking/unlocking of the inner tube to the gripper member and of the inner tube in the outer tube, achieving this with only a translational movement of the gripper member over a travel A or a travel B. The system according to the invention advantageously constitutes a system for inserting and extracting a specimen holder tube intended to house a specimen of nuclear materials, such as nuclear fuels, into and from a measurement instrumentation holder tube intended to house measurement sensors and a cooling system. | 06-05-2014 |
| 20140192945 | FUEL ROD AUTO-LOADING APPARATUS FOR NUCLEAR FUEL ASSEMBLY - Disclosed is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit. | 07-10-2014 |
| 20140205050 | NUCLEAR FUEL ASSEMBLY HANDLING APPARATUS - A fuel assembly handling tool that can be lowered onto the top nozzle of a fuel assembly, positively latch the top nozzle, unlatch from the top nozzle, and be raised off the top nozzle of the fuel assembly. The tool head, that interfaces with the top nozzle has load bearing grippers that latch onto the fuel assembly, that are located in a storage position up within the tool while the tool is lowered onto the fuel assembly. The gripper fingers are then lowered into position during the latching process, and are raised back to the storage position during the unlatching process. In the storage position, the gripping fingers are spaced above the fuel assembly top nozzle when the tool head is resting on the nozzle. | 07-24-2014 |
| 20160035447 | Integrated System for Forming and Transporting Packaging Assemblies, and the Assembly, Filling and Disassembly Stations Thereof - The invention relates to an assembly consisting of a plurality of packaging bottles ( | 02-04-2016 |
| 20160042821 | VOLOXIDIZER WITH DOUBLE REACTOR FOR SPENT FUEL RODS DECLADDING AND DOUBLE REACTOR FOR USE IN THE SAME - A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated. | 02-11-2016 |
| 376262000 | Including handling of a second different, diverse reactor component (e.g., control element, moderator element, vessel cover removal) | 7 |
| 20080205576 | LIGHT WATER REACTOR, CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY - A light water reactor, comprising: | 08-28-2008 |
| 20090129528 | Method and apparatus for permissive control of a mast and grapple - A method and apparatus for the permissive control of a mast and fuel grapple to be used in the movement of reactor fuel components, including fuel assemblies, single blade and double blade guides, to be used in a Boiling Water Reactor (BWR) nuclear reactor. The Permissive Control System reduces the chance of human error associated with the movement of reactor components by assisting in controlling the location (plant coordinate) of the mast for picking-up and dropping-off reactor components, the sequence of reactor component movements, the orientation (angular rotation) of the mast and fuel grapple, the raising and lowering of the grapple, and the opening and closing of the fuel grapple. | 05-21-2009 |
| 20110317797 | CONTROL ROD/FUEL SUPPORT HANDLING APPARATUS - A control rod/fuel support handling apparatus that is used in the case where a control rod and a fuel support are held, removed and lifted in a reactor and then are transported into the reactor in a periodical inspection of a BWR and in the case where the control rod and the fuel support are attached and mounted again into the reactor, the control rod/fuel support handling apparatus including: a fuel support gripper that holds the fuel support with a support gripping member; a control rod gripper that includes a vertically movable and rotatable elevating/rotating unit, holds the control rod with a control rod gripping member, disconnects and connects the control rod and a control rod drive mechanism, and allows removal and attachment of the control rod; and a control panel that controls automatically controls the control rod gripper in response to the instructions from an operation pendant. | 12-29-2011 |
| 20130301779 | SMALL MODULAR REACTOR REFUELING SEQUENCE - A nuclear reactor includes at least: a pressure vessel including an upper vessel section and a lower vessel section connected by a mid-flange and containing primary coolant; a nuclear reactor core disposed in the lower vessel section and immersed in the primary coolant; and upper internals suspended from the mid-flange of the pressure vessel. The upper internals include at least internal CRDMs immersed in the primary coolant and control rod guide frames. To refuel, the nuclear reactor is depressurized. The upper vessel section is disconnected and removed while leaving the mid-flange in place with the upper internals remaining suspended from the mid-flange. The mid-flange is then removed with the upper internals remaining suspended from the mid-flange. The fuel is replaced, the mid-flange is placed back onto the lower vessel section with the upper internals remaining suspended from the mid-flange, and the upper vessel section is placed back and re-connected. | 11-14-2013 |
| 20160027539 | SYSTEMS AND METHODS OF REMOTE CONTROL ROD DRIVE DECOUPLING - Systems join with a control rod drive and expand or contract to displace elements necessary for decoupling. Joining structures affix to on sides of the control rod drive allow discriminatory jacking by a powered drive also in contact with the control rod drive. A moveable piston tube can be displaced by this jacking with hundreds or thousands of pounds of force with respect to the control rod drive. Probes and other instrumentation and sensors are useable in the systems to accurately measure any of piston tube displacement, temperature, malfunction; drive power status, displacement or speed; and communications status. Manual interaction with the systems are not required during the jacking, and installation and removal of the systems requires no tools or great amount of time or effort. Through remote operation and brief installation, human exposure to radiation about control rod drives is minimized. | 01-28-2016 |
| 376263000 | With pressure vessel cover removal | 2 |
| 20100098205 | MODULAR REACTOR HEAD AREA ASSEMBLY - Provided is a modular reactor head area assembly. The modular reactor head area assembly is installed on a reactor head, and includes: a seismic support structure that performs functions of lifting, moving and reinstallation of the reactor head and control rod driving apparatuses, cooling of the control rod driving apparatuses, shielding of missile parts, and supporting with respect to a seismic load, and disperses a load applied to the control rod driving apparatuses; an upper module that is an assembly of components located at an upper portion of the seismic support structure for the control rod driving apparatuses; and a lower module that is an assembly of components located at a lower portion of the seismic support structure for the control rod driving apparatuses. The upper module and the lower module are | 04-22-2010 |
| 20120027155 | Integrated Reactor Missile Shield and Crane Assembly - An integrated reactor missile shield and crane assembly (IRMSCA) is disclosed and claimed. The IRMSCA replaces the existing concrete missile shields and reactor services crane. The IRMSCA is moveable such that the missile shield can be moved away from the reactor head, allowing the integral crane to lift the control rod drive mechanism components and other routine loads at the refueling cavity. | 02-02-2012 |
| 376264000 | Charging or discharging of fuel | 28 |
| 20090285346 | APPARATUS FOR ASSISTING THE LOADING OR UNLOADING OF A CORE IN A PRESSURIZED-WATER REACTOR - An apparatus for loading and unloading a core of a pressurized water reactor exerts a force acting transversely to an axial direction of a fuel assembly against an upper region of a fuel assembly adjacent a fuel assembly unloading or loading position of the core. The apparatus is an immersion vehicle being freely maneuverable under water and on which an extendable carrier arm is disposed and at least indirectly positioned against the fuel assembly. | 11-19-2009 |
| 20100142667 | DEVICE FOR HANDLING A FUEL ASSEMBLY - The invention refers to a device and a method for handling a fuel assembly ( | 06-10-2010 |
| 20110110484 | Standing wave nuclear fission reactor and methods - Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor. | 05-12-2011 |
| 20110164718 | DEVICE FOR GRIPPING FUEL ELEMENTS, ASSOCIATED CLAMP AND ASSOCIATED HANDLING SYSTEM - A fuel element handling system having a gripping device, the structure of which can be pushed in the horizontal position and uncoupled from the handling system if a failure occurs, uncoupling releasing the load formed by the fuel elements and their gripped support and putting them in a safe situation. | 07-07-2011 |
| 20110206173 | SMALL, FAST NEUTRON SPECTRUM NUCLEAR POWER PLANT WITH A LONG REFUELING INTERVAL - Nuclear reactor systems and methods are described having many unique features tailored to address the special conditions and needs of emerging markets. The fast neutron spectrum nuclear reactor system may include a reactor having a reactor tank. A reactor core may be located within the reactor tank. The reactor core may include a fuel column of metal or cermet fuel using liquid sodium as a heat transfer medium. A pump may circulate the liquid sodium through a heat exchanger. The system may include a balance of plant with no nuclear safety function. The reactor may be modular, and may produce approximately 100 MW | 08-25-2011 |
| 20120027156 | ANNULAR CORE LIQUID-SALT COOLED REACTOR WITH MULTIPLE FUEL AND BLANKET ZONES - A liquid fluoride salt cooled, high temperature reactor having a reactor vessel with a pebble-bed reactor core. The reactor core comprises a pebble injection inlet located at a bottom end of the reactor core and a pebble defueling outlet located at a top end of the reactor core, an inner reflector, outer reflector, and an annular pebble-bed region disposed in between the inner reflector and outer reflector. The annular pebble-bed region comprises an annular channel configured for receiving pebble fuel at the pebble injection inlet, the pebble fuel comprising a combination of seed and blanket pebbles having a density lower than the coolant such that the pebbles have positive buoyancy and migrate upward in said annular pebble-bed region toward the defueling outlet. The annular pebble-bed region comprises alternating radial layers of seed pebbles and blanket pebbles. | 02-02-2012 |
| 20120128113 | REMOTE CONTROL SYSTEM FOR THE FUEL HANDLING SYSTEM OF NUCLEAR POWER PLANT - Disclosed is a remote control system for a fuel handling system of a nuclear power plant, in which the system includes a remote control console; a programmable logic controller (PLC) unit; a servo motor drive; and a human-machine interface (HMI) unit. | 05-24-2012 |
| 20130044850 | NUCLEAR REACTOR REFUELING METHODS AND APPARATUSES - Refueling of a nuclear reactor ( | 02-21-2013 |
| 20130301780 | NUCLEAR FUEL CONTAINING A NEUTRON ABSORBER - Fuel bundles for a nuclear reactor are described and illustrated, and in some cases include fuel elements each having a fissile content of | 11-14-2013 |
| 20130315363 | DEVICE AND METHOD FOR REPLACING AN IRRADIATED FUEL ASSEMBLY WITH A NEW FUEL ASSEMBLY IN THE VESSEL OF A NUCLEAR REACTOR, AND NUCLEAR REACTOR INCLUDING SUCH A DEVICE - A device and a method to replace an irradiated fuel assembly with a new fuel assembly in the vessel of a nuclear reactor. This device includes: means for installing the two fuel assemblies in two containers containing heat transfer fluid, where the first container is filled with the irradiated fuel assembly having just been extracted from the reactor core by a handling arm, and where the second container is filled with the new fuel assembly brought in by a transfer basket, means for positioning both these containers, where the irradiated fuel assembly is accessible by the transfer basket, whereas the new fuel assembly is in a position where it can be taken up by the handling arm, and means for positioning both the fuel assemblies. | 11-28-2013 |
| 20160148710 | NUCLEAR FISSION IGNITER - Illustrative embodiments provide nuclear fission igniters for nuclear fission reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, a nuclear fission igniter configured to ignite a nuclear fission deflagration wave in nuclear fission fuel material, a nuclear fission deflagration wave reactor with a nuclear fission igniter, a method of igniting a nuclear fission deflagration wave, and the like. | 05-26-2016 |
| 376265000 | Refueling ball-type reactors | 2 |
| 20080298534 | Nuclear Plant with a Pebble Bed Nuclear Reactor - This invention relates to a nuclear plant including a main power system and a fuel handling and storage system. The system is connected to a sphere inlet and a sphere outlet of a multi-pass high temperature gas cooled pebble bed reactor. The system is configured such that gas flows from the system into the reactor through both the sphere inlet and the sphere outlet thereby inhibiting the ingress of high temperature gas from the reactor into the system. Restricting indexers permit the movement of spheres between the reactor and the system and dampen out the transmission of pressure fluctuations from the power system to the system. | 12-04-2008 |
| 20120230458 | NUCLEAR PLANT WITH A PEBBLE BED NUCLEAR REACTOR - This invention relates to a nuclear plant including a main power system and a fuel handling and storage system. The system is connected to a sphere inlet and a sphere outlet of a multi-pass high temperature gas cooled pebble bed reactor. The system is configured such that gas flows from the system into the reactor through both the sphere inlet and the sphere outlet thereby inhibiting the ingress of high temperature gas from the reactor into the system. Restricting indexers permit the movement of spheres between the reactor and the system and dampen out the transmission of pressure fluctuations from the power system to the system. | 09-13-2012 |
| 376267000 | Refueling schemes, patterns, or fuel cycles (e.g., in/out systems) | 15 |
| 20090196391 | Core of a Boiling Water Reactor - A core of a boiling water reactor as a burner type core of the boiling water reactor having a ratio of 3 or more of number of fuel assemblies loaded in the core to number of control rods installed in the nuclear reactor and using an oxide of low enriched uranium having a mean enrichment of the fuel assemblies of 3 wt % to 8 wt % or a mixed oxide having a mean fissile plutonium enrichment of the fuel assemblies of 2 wt % to less than 7 wt %, | 08-06-2009 |
| 20090213979 | NUCLEAR POWER STATION COMPRISING AT LEAST ONE HIGH TEMPERATURE REACTOR - The invention relates to a nuclear power station comprising:
| 08-27-2009 |
| 20100208858 | METHOD FOR SELECTING A LOADING MAP FOR A NUCLEAR REACTOR CORE, CORRESPONDING SELECTION SYSTEM, COMPUTER PROGRAM AND STORAGE MEDIIUM - A method for selecting a loading map for a nuclear reactor core including the following steps: a) providing production data relating to the nuclear fuel assemblies, b) providing neutron data which are representative of the operation of the core, c) calculating the three-dimensional distribution of the local power in the core, d) calculating the extreme value reached by at least one thermomechanical parameter within the nuclear fuel assemblies, and e) selecting, in accordance with the extreme values calculated, a loading map from the loading maps envisaged. | 08-19-2010 |
| 20110069803 | Movement of Materials in a Nuclear Reactor - Illustrative embodiments provide for the operation and simulation of the operation of fission reactors, including the movement of materials within reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like. | 03-24-2011 |
| 20110150163 | PROCESS FOR APPLICATION OF LUBRICANT TO FUEL ROD DURING FUEL ASSEMBLY LOADING PROCESS - The present invention relates generally to nuclear reactors, and more particularly, to nuclear reactors having fuel assemblies that employ support grids. A method of reducing friction and physical contact between a fuel rod and support grid in a nuclear fuel assembly is provided. The method includes applying a lubricant composition to the outer surface of the fuel rod during fuel assembly fabrication and removing the lubricant composition afterward. | 06-23-2011 |
| 20120069948 | Method for Joint Configuration of Nuclear Power Plant Fuel - A method for joint configuration of nuclear power plant fuel includes the following steps: (S1) for at least one operating unit, based on an equilibrium cycle or transition cycle reactor core design, at least one new fuel element is added to at least one operating unit; (S2) after running a combustion cycle, and on basis of the new fuel elements in step (S1), more first spent fuel elements are obtained from the at least one operating unit than are obtained from the equilibrium cycle or transition cycle reactor core design, and said first spent fuel elements are kept in reserve; (S3) for at least one new starting unit, a scheduled number of new fuel elements, as well as the first spent fuel elements obtained for reserve in step (S2), are set in the first reactor cores of at least one new starting unit. | 03-22-2012 |
| 20120163525 | METHOD OF OPERATING A PRESSURIZED-WATER NUCLEAR REACTOR FOR REACHING A PLUTONIUM EQUILIBRIUM CYCLE - A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for an initial cycle during which a core contains initial nuclear fuel assemblies; then operating the nuclear reactor for transition cycles, at least some of the initial nuclear fuel assemblies being progressively replaced, during the replacement steps preceding the transition cycles, with transition nuclear fuel assemblies or with plutonium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains only plutonium-equilibrium nuclear fuel assemblies. | 06-28-2012 |
| 20120189089 | METHOD OF OPERATING A PRESSURIZED-WATER NUCLEAR REACTOR ALLOWING SAME TO PASS FROM A PLUTONIUM-EQUILIBRIUM CYCLE TO A URANIUM- EQUILIBRIUM CYCLE AND CORRESPONDING NUCLEAR FUEL ASSEMBLY - A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains plutonium-equilibrium nuclear fuel assemblies; subsequently, operating the reactor for transition cycles, at least some of the plutonium-equilibrium nuclear fuel assemblies being progressively replaced with transition nuclear fuel assemblies and then with uranium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one uranium equilibrium cycle. | 07-26-2012 |
| 20120243650 | NUCLEAR INSTALLATION - A nuclear installation | 09-27-2012 |
| 20120294406 | ADVANCED FIRST CORE FUEL ASSEMBLY CONFIGURATION AND METHOD OF IMPLEMENTING THE SAME - An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. A method of implementing such an initial core involves providing a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed. | 11-22-2012 |
| 20130121452 | PRESSURE-TUBE REACTOR WITH PRESSURIZED MODERATOR - A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator. | 05-16-2013 |
| 20140334587 | SYSTEM FOR HANDLING FUEL ELEMENTS - Fuel elements are moved between an upper pool and a lower pool of a nuclear plant by a conveyor tube having an upper end at the upper pool and a lower end at the lower pool and extending at an acute angle to the vertical between the ends. A plurality of transport baskets can move through the conveyor tube, each holding at least one of the fuel. An upper transfer device at the upper end in the upper pool loads the fuel elements into or unloads them from the transport baskets. A lower transfer device in the lower pool loads fuel elements into or unloads them from the transport baskets. Each transfer device can hold two of the transport baskets that are displaceable for positioning above or below the conveyor tube and movable during displacement through the tube between a vertical transfer position and an angled transport position. | 11-13-2014 |
| 20140334588 | SYSTEM FOR HANDLING FUEL ELEMENTS - A system for transferring fuel elements between an upper pool and a lower pool of a nuclear plant has a conveyor tube having an upper end at the upper pool and a lower end at the lower pool. A transport basket movable internally along the tube and into which at least one of the fuel elements can be placed can travel through the conveyor tube. A blocking element at one end of the tube that can fully close the conveyor tube at the respective end. A cable hoist has a traction cable guided through the conveyor tube for raising and lowering the transport basket through the conveyor tube. An intermediate partially closing blocking element offset from the fully closing blocking element in the tube is formed with a cable passage through which the traction cable can pass in the closed position. | 11-13-2014 |
| 20140334589 | APPARATUS FOR HANDLING FUEL ELEMENTS - A system for transfer of fuel elements between an upper pool and a lower pool of a nuclear plant has a conveyor tube having an upper end in the upper pool and a lower end in the lower pool, formed below the upper end with a laterally open port, and extending between the ends at an acute angle to the vertical. A transport basket into which the fuel elements can be placed can be moved through the conveyor tube by a cable hoist having a cable winch outside the tube and a traction cable guided through the conveyor tube and out of the port and extending along and inside the tube. An upper blocking element can close the upper end of the conveyor tube. The cable port is preferably formed by a lateral hole in the conveyor tube preferably provided directly below the upper blocking element. | 11-13-2014 |
| 20160111174 | ADVANCED FIRST CORE FUEL ASSEMBLY CONFIGURATION - An advanced initial core fuel configuration is for improving the fuel management efficiency and thus economics for a nuclear reactor. The advanced initial core fuel configuration includes a plurality of fuel assemblies having different average enrichments of uranium 235 and arranging the fuel assemblies in an initial core configuration structured to emulate a known equilibrium reload cycle core at least in terms of spatial reactivity distribution. The resulting average enrichment within the initial core ranges from below about 1.0 percent weight of uranium 235 to about 5.0 percent weight of uranium 235. An advanced lattice design is also disclosed. | 04-21-2016 |
