| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376426000 |
Plural fuel segments or elements
| 120 |
| 376412000 |
Encased with nonfuel component
| 88 |
| 376451000 |
Having particular end closure or seal (e.g., weld, plug, cap, etc.)
| 8 |
| 376411000 |
Spherical particles | 3 |
| 20090129533 | Nuclear fuel - This invention relates to a method of preparing nuclear fuel including the step of depositing at least two adjacent series of layers ( | 05-21-2009 |
| 20100014625 | SPHERICAL FUEL ELEMENT AND PRODUCTION THEREOF FOR GAS-COOLED HIGH TEMPERATURE PEBBLE BED NUCLEAR REACTORS (HTR) - The invention relates to a novel design and production of fuel element pebbles which satisfy the requirements of high temperature pebble bed nuclear reactors of the next generation. The invention uses a shell of the fuel element pebbles that is devoid of fuel and consists of silicon carbide (SiC) and/or zircon carbide (ZrC), in addition to natural graphite and graphitized petroleum coke, said shell having a maximum average nominal thickness of 5 mm and preferably only 3 mm. | 01-21-2010 |
| 20100296621 | METHOD OF MANUFACTURING NUCLEAR FUEL ELEMENTS AND A CONTAINER FOR IMPLEMENTING SUCH A METHOD - A method of manufacturing nuclear fuel elements comprising the steps of placing nuclear fuel balls in the container made from ultra-porous material, applying a CVI to the container and removing the container. The container for manufacturing fuel elements comprising balls, and is produced from at least one ultra-porous material, for example carbon foam. | 11-25-2010 |
| 376456000 |
Vented fuel | 3 |
| 20110051881 | Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system - Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system. | 03-03-2011 |
| 20110058638 | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system - Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system. | 03-10-2011 |
| 20110150167 | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system - Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system. | 06-23-2011 |
| 376450000 |
With condition sensing or indicating means | 2 |
| 20090122948 | Method of Determining at Least One Technological Uncertainty Factor for Nuclear Fuel Elements, and Corresponding Methods of Designing, Fabricating, and Inspecting Nuclear Fuel Elements - The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements ( | 05-14-2009 |
| 20110170654 | NUCLEAR FUEL PELLET INSPECTION - A system for inspecting nuclear fuel pellets is provided. The inspection system is configured to use X-ray radiation at one or more energies to probe nuclear fuel pellets disposed within a nuclear fuel rod for nuclear fuel pellet defects. In some implementations of the inspection system, a nuclear fuel rod manufacturing facility may be able to integrate the inspection system for fully or partially automated inspection of all fuel rods produced within the facility. | 07-14-2011 |
| 376457000 |
Nonconventional jacket or can material | 2 |
| 20120045030 | METHOD FOR FORMING ROUGHNESS ON SURFACE OF NUCLEAR FUEL ROD CLADDING INCLUDING ZIRCONIUM - A method for forming roughness on an outer surface of cladding of a fuel nuclear rod including zirconium includes: positioning the cladding of the nuclear fuel rod at a first electrode and connecting a positive electrode thereto, and positioning a conductive plate at a second electrode and connecting a negative electrode thereto; putting the cladding of the nuclear fuel rod in an electrolyte solution; and applying voltage to the positive electrode and the negative electrode to cause oxidation on the outer surface of the cladding of the nuclear fuel rod. In this case, the electrolyte solution is maintained at 10° C. or lower. | 02-23-2012 |
| 20180025793 | COLD SPRAY CHROMIUM COATING FOR NUCLEAR FUEL RODS | 01-25-2018 |
| 376453000 |
Fuel support or covering provided with fins, projections, prongs, etc.) | 2 |
| 20160203879 | OPTIMIZED FUEL ASSEMBLY CHANNELS AND METHODS OF CREATING THE SAME | 07-14-2016 |
| 20220139575 | FUEL ASSEMBLY WITH OUTER CHANNEL INCLUDING REINFORCED SIDEWALL - The fuel assembly includes at least one fuel rod and an outer channel with four sidewalls surrounding the fuel rod, the outer channel having a configuration based on a position of the fuel assembly within a core of the nuclear reactor, wherein at least a first select sidewall, of the four sidewalls of the outer channel, is a reinforced sidewall, the remaining sidewalls of the outer channel, other than the at least a first select sidewall, are non-reinforced sidewalls, the at least a first select sidewall being in a controlled location that faces and is directly adjacent to a control blade that is to be utilized in the nuclear reactor, wherein an entirety of the reinforced sidewall as a whole is at least one of thicker and made from a material that is more resistant to radiation-induced deformation as compared to an entirety of the non-reinforced sidewalls. | 05-05-2022 |
| 376455000 |
Hollow, annular, or graduated fuel layers or members (e.g., concentric, helical, etc.) | 1 |
| 20130070890 | GROOVED NUCLEAR FUEL ASSEMBLY COMPONENT INSERT - A nuclear fuel assembly component such as a control rod that has a cylindrical insert such as neutron absorbing material that is closely received within a cladding that is sealed at either end with end caps. The cylindrical member has grooves formed in its side wall extending from an upper surface to a lower surface to permit air to escape from the cladding as the cylindrical member is loaded into the cladding during manufacture. | 03-21-2013 |
| Entries |
| Document | Title | Date |
|---|
| 20080240333 | 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. | 10-02-2008 |
| 20080310577 | FUEL CHANNEL FASTENER - A fuel channel fastener having a body with a hole, a bolt inserted into the hole, at least two anti-rotation supports attached to the body, a spring configured to attach to the body and to extend away from the body down the sides of a fuel assembly fuel channel, and at least two spring anti-rotation pads connected to the body. | 12-18-2008 |
| 20090268861 | Plutonium/Zirconium Hydride/Thorium Fuel Matrix - The present invention is directed to a plutonium-based nuclear fuel that is suitable for burning weapon-grade and reactor-grade plutonium in a light water reactor, thereby reducing the amount of such material that could potentially be used to manufacture a weapon. In one embodiment, the fuel is comprised of plutonium, zirconium hydride, and thorium, with the zirconium hydride comprising more than about 20% by weight of the fuel. | 10-29-2009 |
| 20100061503 | Pseudo-capacitor structure for direct nuclear energy conversion - Direct nuclear energy conversion into electricity device based on nano-hetero-structures with applications in nuclear reactors and radioisotope batteries. The nano structure may be made by a repeated customized sequence of nano-layers generically called “CIci” The structure may also be made by a series of structures evolved from CIci as nanoplasmon, nanowire, nano-tube. The Structure relies on knock on electron avalanche produced by stopping radiation that is generated by the high electron density conductor material “C” that tunnels through insulator “I” and accumulates in the low density conductor “c”. The “C” material is producing no electrons to cross the associate insulator “i” therefore remains negatively charged by the electron shower, and discharges through a resistor connected to th “C” later. The nanoplasmon structure exhibits thermal direct conversion properties by radiation switched mechanism that is generated by the plasmon-phonon resonance. The device has ultra-capacitive properties when made with carbon nanotubes. The device is useful for a direct conversion nano-battery or for nuclear reactor direct conversion structure. It may also be used as a radiation energy harvesting device when made with actinides for neutro-capture and amplification. | 03-11-2010 |
| 20100150300 | NUCLEAR FUEL IN THE FORM OF A PELLET, WITH IMPROVED STRUCTURE - A pellet including a nuclear fuel material for applications in reactors. The pellet has an elongated shape along an axis (z) and includes on an outer radial surface at least one privileged breaking area (R | 06-17-2010 |
| 20110080987 | MANUFACTURING METHOD OF NUCLEAR FUEL PELLET, FUEL ASSEMBLY FOR NUCLEAR REACTOR AND MANUFACTURING METHOD THEREOF AND URANIUM POWDER - Among fuel rods constituting a fuel assembly, Gd compound oxide is added to low Gd containing fuel rods that containing uranium dioxide of which enrichment exceeds 5 wt %. The Gd compound oxide is oxide of gadolinium and rare earth element A except for gadolinium and is expressed as a chemical formula A | 04-07-2011 |
| 20110150166 | METHOD OF PROVIDING A NUCLEAR FUEL AND A FUEL ELEMENT PROVIDED BY SUCH A METHOD - A nuclear fuel element including a uranium-molybdenum alloy that provides an enhanced reactivity in research, test and radioisotope production nuclear reactors. In this uranium-molybdenum alloy, the uranium is enriched in the isotope 235-U, while the molybdenum is depleted in the isotope 95-Mo. The thus obtained enhanced reactivity provides, depending on the exact use of the fuel element, a requirement for less uranium in the fuel and the use of the fuel elements during a longer period in the reactor. | 06-23-2011 |
| 20110158374 | ALLOY AND TUBE FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR MAKING SAME - The invention concerns an alloy containing equally 0.02 to 0.07% wt. % of the total iron, of chromium or vanadium, 0.8 to 1.3 wt. % of niobium, 100 ppm or less of tin, 1100 to 1700 ppm of oxygen, less than 100 ppm of carbon, 10 to 30 ppm of sulphur and less than 50 ppm of silicon. | 06-30-2011 |
| 20120039431 | Process for fused neutron nuclear chain reactions - Fused neutron particles from a multi-neutron particle generator are injected into atomic nuclei that have a core with groups of fused neutron pairs. Nuclear fusion reactions between injected multi-neutron particles and atomic core neutron particle pairs produce binding energy which causes atomic nuclei to fission. Consequently, more binding energy is released and fused neutron particle pairs are ejected from the nucleus. The ejected fused neutron particle pairs then enter nuclei of other atoms to cause nuclear fusion and nuclear fission reactions. More binding energy and more fused neutron particle pairs are released from the nuclei. This is a chain reaction process that can produce nuclear binding energy from almost any element as fuel. | 02-16-2012 |
| 20120183116 | COMPOSITE NUCLEAR FUEL PELLET - A composite nuclear fuel pellet comprises a composite body including a UO2 matrix and a plurality of high aspect ratio particies dispersed therein, where the high aspect ratio particies have a thermal conductivity higher than that of the UO2 matrix. A method of making a composite nuclear fuel pellet includes combining UO2 powder with a predetermined amount of high aspect ratio particles to form a combined powder, the high aspect ratio particles having a thermal conductivity higher than that of the UO2 powder; mixing the combined powder in a solvent to disperse the high aspect ratio particles in the UO2 powder; evaporating the solvent to form a dry mixture comprising the high aspect ratio particles dispersed in the UO2 powder; pressing the dry mixture to form a green body; and sintering the green body to form the composite fuel pellet. | 07-19-2012 |
| 20120257707 | Nuclear fuel and method of fabricating the same - A nuclear fuel includes a volume of a nuclear fuel material defined by a surface, the nuclear fuel material including a plurality of grains, some of the plurality of grains having a characteristic length along at least one dimension that is smaller than or equal to a selected distance, wherein the selected distance is suitable for maintaining adequate diffusion of a fission product from a grain interior to a grain boundary in some of the grains, the nuclear fuel material including a boundary network configured to transport the fission product from at least one grain boundary of some of the grains to the surface of the volume of the nuclear fuel material. | 10-11-2012 |
| 20120314831 | Light Water Reactor TRISO Particle-Metal-Matrix Composite Fuel - A metal matrix, microencapsulated nuclear fuel component includes an integral metal matrix having an outer buffer region and an inner fuel containing region; a multiplicity of nuclear fuel capsules embedded in the fuel containing region of the matrix for encapsulating a nuclear fuel particle and products resulting from nuclear and chemical reactions; and a nuclear fuel particle encapsulated in each of the nuclear capsules. | 12-13-2012 |
| 20130148774 | POROUS UO2 SINTERED PELLETS AND METHOD FOR FABRICATING POROUS UO2 SINTERED PELLETS AND ELECTROLYTIC REDUCTION USING SAME - A method for fabricating porous UO | 06-13-2013 |
| 20140153687 | FUEL COMPONENT AND METHOD OF MANUFACTURING OF A FUEL COMPONENT - The invention relates to a fuel component and a method for manufacturing of a fuel component. The fuel component is adapted to be used in fission reactors. The fuel component comprises a core consisting of a first material, and a layer consisting of a second material. The layer encloses at least partly the core. The first material comprises a fissile substance. The fuel component comprises an intermediate layer between the core and the layer. The intermediate layer has a material gradient that comprises a decrease of the concentration of the first material from the core to the layer and an increase of the concentration of the second material from the core to the layer. | 06-05-2014 |
| 20140153688 | MULTILAYER TUBE IN CERAMIC MATRIX COMPOSITE MATERIAL, RESULTING NUCLEAR FUEL CLADDING AND ASSOCIATED MANUFACTURING PROCESSES - The invention relates to a multilayer tubular part (1) comprising a metal layer forming a metal tubular body (3) and two layers in ceramic matrix composite material covering the metal tubular body, wherein one of the two layers in ceramic matrix composite material covers the inner surface of the metal tubular body to form an inner tubular body (4), whilst the other of the two layers in ceramic matrix composite material covers the outer surface of the metal tubular body to form an outer tubular body (2), the metal tubular body therefore being sandwiched between the inner and outer tubular bodies. The metal tubular body is in metal or metal alloy. Finally, the metal tubular body has a mean thickness smaller than the mean thicknesses of the inner and outer tubular bodies. A said part is useful in particular for producing nuclear fuel claddings. | 06-05-2014 |
| 20140211904 | Heterogeneous Core Designs And Thorium Based Fuels For Heavy Water Reactors - A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided. | 07-31-2014 |
| 20140341331 | NUCLEAR FUEL ASSEMBLY DESIGN - A duct for a nuclear fuel assembly includes a tubular body and an elongated member. The tubular body has a sidewall with an inner face and an outer face and is configured to contain nuclear fuel within a fuel region. The elongated member extends from the outer face along at least a portion of the fuel region and has a contact surface configured to stabilize the duct during operation of the nuclear fuel assembly. | 11-20-2014 |
| 20150302942 | OXIDE NUCLEAR FUEL WHICH IS A REGULATOR OF CORROSIVE FISSION PRODUCTS, ADDITIVATED WITH AT LEAST ONE OXIDATION-REDUCTION SYSTEM - A supplemented nuclear fuel comprises a nuclear fuel of oxide type which generates fission products such as tellurium, cesium and iodine, which generate via chemical interaction species that are potentially corrosive, supplemented with at least one redox system comprising a first and second species comprising a common element having a different degree of oxidation in each of the two species, the system having an oxygen potential curve as a function of the temperature that is within an interval delimited by:
| 10-22-2015 |
| 20150340110 | METHOD FOR PRODUCING NUCLEAR FUEL PRODUCTS WITH A HIGH LOADING OF LEU AND CORRESPONDING NUCLEAR FUEL PRODUCT - A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The core has a low-enriched uranium loading strictly higher than 3.0 gU/cm | 11-26-2015 |
| 20150348652 | DEPOSITION OF A PROTECTIVE COATING INCLUDING METAL-CONTAINING AND CHROMIUM-CONTAINING LAYERS ON ZIRCONIUM ALLOY FOR NUCLEAR POWER APPLICATIONS - The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The coating includes a first tier or layer and a second tier or layer. The first layer includes an elemental metal and the second layer is an oxidation-resistant layer that includes elemental chromium. The first layer serves as an intermediate layer between the zirconium alloy substrate and the second layer. This intermediate layer can be effective to improve adhesion of the second layer to the zirconium alloy substrate. The multilayer coating forms a protective layer which provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear reactor. | 12-03-2015 |
| 20160035441 | FUEL ASSEMBLY - A fuel assembly for use in a core of a nuclear power reactor. The assembly includes a frame shaped and configured to fit within the nuclear reactor internal core structure; and a plurality of helically twisted fuel elements supported by the frame in a fuel rod bundle. Each of the fuel elements includes fissile material. When viewed in a cross-section that is perpendicular to an axial direction of the fuel assembly, the outermost fuel elements of the fuel rod bundle define a substantially circular perimeter. Other features, and a nuclear reactor, are also described. | 02-04-2016 |
| 20160055923 | FUEL CHANNEL FOR A NUCLEAR POWER BOILING WATER REACTOR - A fuel channel for a nuclear power boiling water reactor is configured to include a bundle of fuel rods with nuclear fuel. The fuel channel is made of a sheet material and has a plurality of sides which have an elongated shape and which are connected to each other such that a corner with an elongated shape is formed where two adjacent sides meet. In one or more corners, the sheet materials from the two adjacent sides overlap with each other such that there is a corner region with double sheet material consisting of the overlapping sheet material from one of the two sides and the overlapping sheet material from the other of the two sides. | 02-25-2016 |
| 20180025794 | SPRAY METHODS FOR COATING NUCLEAR FUEL RODS TO ADD CORROSION RESISTANT BARRIER | 01-25-2018 |
