| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376412000 | Encased with nonfuel component | 88 |
| 20090060115 | METHOD, USE AND DEVICE CONCERNING CLADDING TUBES FOR NUCLEAR FUEL AND A FUEL ASSEMBLY FOR A NUCLEAR PRESSURE WATER REACTOR - A method of producing a cladding tube for nuclear fuel for a nuclear pressure water reactor includes forming a tube which at least principally consists of a cylindrical tube component of a zirconium-based alloy, where the alloying element, except for zirconium, which has the highest content in the alloy is niobium, wherein the niobium content in weight percent is between about 0.5 and about 2.4 and wherein no alloying element, except for zirconium and niobium, in the alloy, has a content which exceeds about 0.2 weight percent. The cladding tube is then annealed such that the tube component is partly but not completely recrystallized. The degree of recrystallization in the tube component is higher than about 40% and lower than about 95%. A fuel assembly for a nuclear pressure water reactor also has a plurality of such cladding tubes. | 03-05-2009 |
| 20090080591 | NUCLEAR FUEL PROVIDED WITH A COATING - This invention relates to a method of preparing a nuclear fuel including the step of depositing a coating which includes fluorine, or at least one compound thereof, around a kernel ( | 03-26-2009 |
| 20090080592 | Swelling-resistant nuclear fuel - A nuclear fuel according to one embodiment includes an assembly of nuclear fuel particles; and continuous open channels defined between at least some of the nuclear fuel particles, wherein the channels are characterized as allowing fission gasses produced in an interior of the assembly to escape from the interior of the assembly to an exterior thereof without causing significant swelling of the assembly. Additional embodiments, including methods, are also presented. | 03-26-2009 |
| 20090252278 | NUCLEAR REACTOR (ALTERNATIVES), FUEL ASSEMBLY OF SEED-BLANKET SUBASSEMBLIES FOR NUCLEAR REACTOR (ALTERNATIVES), AND FUEL ELEMENT FOR FUEL ASSEMBLY - The invention relates to light water reactor designs in which thorium is used as fuel and in particular to designs of jacketless fuel assemblies, which make up the cores of pressurized water reactors (PWRs) such as the VVER-1000. Nuclear reactor cores containing seed and blanket subassemblies that make up the fuel assemblies are used to burn thorium fuel together with conventional reactor fuel that includes nonproliferative enriched uranium, as well as weapons-grade and reactor-grade plutonium. In the first alternative, the reactor core is fully “nonproliferative,” since neither the reactor fuel nor the wastes generated can be used to produce nuclear weapons. In the second version of the invention, the reactor core is used to burn large amounts of weapons-grade plutonium together with thorium and provides a suitable means to destroy stockpiles of weapons-grade plutonium and convert the energy released to electric power. The cores in both embodiments of the invention are made up of a set of seed-blanket assemblies, which have central seed areas surrounded by annular blanket areas. The seed areas contain uranium or plutonium fuel rods, while the blanket areas contain thorium fuel rods. The volume ratio of moderator to fuel and the relative sizes of the seed area and the blanket area have been optimized so that neither embodiment of the invention generates wastes that can be used to produced nuclear weapons. A new refueling system is also used for the first embodiment of the invention to maximize recycling of the seed fuel; the system also ensures that the spent nuclear fuel cannot be used to produce nuclear weapons. | 10-08-2009 |
| 20090285350 | Multi-layer fuel channel and method of fabricating the same - A fuel channel according to example embodiments for a nuclear reactor may have an elongated and hollow body with a multi-layer structure. The multi-layer structure may include a core layer and at least one cladding layer metallurgically-bonded to the core layer. The core layer and the at least one cladding layer may be alloys having different compositions. For instance, the core layer may be significantly more resistant to irradiation growth and/or irradiation creep than the at least one cladding layer, and the at least one cladding layer may have an increased resistance to hydrogen absorption and/or corrosion relative to the core layer. Accordingly, the distortion of the fuel channel may be reduced or prevented, thus reducing or preventing the interference with the movement of the control blade. | 11-19-2009 |
| 20100034335 | ARTICLES HAVING ENHANCED WETTABILITY - Articles having surfaces with enhanced wetting properties are presented. One embodiment is an article having a surface configured for promoting a phase transformation from a liquid phase to a vapor phase. The article comprises an element comprising a surface disposed to be in contact with a liquid to be transformed to a vapor, and the surface comprises a plurality of surface features having a median feature size, a, and a median feature spacing, b, such that the ratio b/a is up to about 8. The surface comprises a material disposed to contact the liquid, and this material has a nominal wettability sufficient to generate a nominal contact angle of up to about 80 degrees with a drop of the liquid. Another embodiment is a fuel rod for a nuclear reactor comprising a surface configured as described above. | 02-11-2010 |
| 20100091932 | METHOD FOR DESIGNING A FUEL ASSEMBLY OPTIMIZED AS A FUNCTION OF THE STRESSES IN USE IN LIGHT-WATER NUCLEAR REACTORS, AND RESULTING FUEL ASSEMBLY - A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method. | 04-15-2010 |
| 20100098207 | METHOD AND DEVICE TO PRODUCE HEAT AND POWER - A method and device are described to form a heat producing plant with replaceable fusion-based reaction cartridges, where the fuel is embedded in casings in the preferred embodiment, and the heat can be converted into electrical or mechanical energy. The replaceable unit consists of sheets containing individual heating elements that are addressed sequentially to trigger the heat producing reactions. A controller governs the triggering activity until all the elements are used. The resulting heat can be converted into mechanical energy using turbines and into electrical energy using the Seebeck effect. This inventive device can be used in mobile environments as well as at fixed locations where heat, mechanical power or electricity are needed. | 04-22-2010 |
| 20100128834 | ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE AND METHOD FOR FABRICATING ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE - Articles, such as tubing or strips, which have excellent corrosion resistance to water or steam at elevated temperatures, are produced from alloys having 0.2 to 1.5 weight percent niobium, 0.01 to 0.45 weight percent iron, at least one additional alloy element selected from 0.02 to 0.8 weight percent tin, 0.05 to 0.5 weight percent chromium, 0.02 to 0.3 weight percent copper, 0.1 to 0.3 weight percent vanadium, 0.01 to 0.1 weight percent nickel, the balance at least 97 weight percent zirconium, including impurities, wherein the alloy may be fabricated from a process of forging the zirconium alloy into a material, beta quenching the material, forming the material by extruding or hot rolling the material, cold working the material with one or a multiplicity of cold working steps, wherein the cold working step includes cold reducing the material and annealing the material at an intermediate anneal temperature of 960°-1105° F., and final working and annealing of the material. The articles formed also show improved weld corrosion resistance with the addition of chromium. | 05-27-2010 |
| 20100135452 | LIQUID-METAL-COOLED FAST REACTOR CORE COMPRISING NUCLEAR FUEL ASSEMBLY WITH NUCLEAR FUEL RODS WITH VARYING FUEL CLADDING THICKNESS IN EACH OF THE REACTOR CORE REGIONS - A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly ( | 06-03-2010 |
| 20100142668 | POROUS PLENUM SPACER FOR DUAL-COOLED FUEL ROD - A porous plenum spacer is inserted into the plenum of a dual-cooled fuel rod having concentric inner and outer cladding tubes. The porous plenum spacer includes a hollow cylindrical body inserted into the annular space between the inner and outer cladding tubes. The hollow cylindrical body includes a plurality of through-holes formed in an outer circumference thereof or at least one groove formed in one of outer and inner circumferences thereof in a lengthwise direction. Pores formed by the through-holes or the grooves of the hollow cylindrical body of the porous plenum spacer are allowed to secure a space containing fission gas inevitably generated by a nuclear reaction. | 06-10-2010 |
| 20100303193 | PARTICULATE METAL FUELS USED IN POWER GENERATION, RECYCLING SYSTEMS, AND SMALL MODULAR REACTORS - A metal particulate fuel system is described. The metal fuel system may include particulate metal fuel for use in nuclear reactors. The particulate metal fuel may include a plurality of particles of at least one enriched alloy where the particles are compacted into a fuel column. The metal particulate fuel system may also include a cladding and/or a gas-filled plenum. | 12-02-2010 |
| 20100322370 | PROCESS OF MANUFACTURING ZIRCONIUM ALLOY FOR FUEL GUIDE TUBE AND MEASURING TUBE HAVING HIGH STRENGTH AND EXCELLENT CORROSION RESISTANCE - A process of manufacturing zirconium alloy. The process may be used to make a nuclear fuel guide tube and/or a measuring tube which are main components of a nuclear fuel assembly structure. While a nuclear fuel guide tube and a measuring tube are manufactured by performing three-step cold working, and intermediate and final thermal annealing from a semi-finished TREX shell in the conventional method, the present invention relates to zirconium alloy undergoing two-step cold working, and intermediate and final thermal annealing from a TREX shell, resulting in enhanced strength and corrosion resistance. The present invention may be applied to a nuclear fuel guide tube and a measuring tube used for a nuclear fuel assembly in a light water nuclear reactor because, by the shortened process, high percentage reduction in thickness between processes and an decrease in thermal annealing time may sustain high strength and excellent corrosion resistance, and achieve economy of manufacture by reducing the number of processes. | 12-23-2010 |
| 20110091004 | TRISO FUEL FOR HIGH BURN-UP NUCLEAR ENGINE - A fuel particle for use in a fusion-fission nuclear engine includes a fuel kernel and a buffer layer surrounding the fuel kernel. The fuel particle also includes a pyrolytic carbon layer surrounding the buffer layer and a silicon carbide layer surrounding the buffer layer. The silicon carbide is characterized by a stress less than 450 MPa at 95% burn-up. The fuel particle further includes a second pyrolytic carbon layer surrounding the silicon carbide layer. | 04-21-2011 |
| 20110176650 | NUCLEAR REACTOR GREEN AND SINTERED FUEL PELLETS, CORRESPONDING FUEL ROD AND FUEL ASSEMBLY - A sintered fuel pellet for a water nuclear reactor fuel rod including a peripheral wall extending along a central axis and two end faces. At least one of the end faces includes at least a first chamfer extending from the peripheral wall towards the central axis with a first non-zero slope with respect to a plane perpendicular to the central axis and a second chamfer extending from the first chamfer towards the central axis with a second non-zero slope with respect to a plane perpendicular to the central axis, wherein the first slope is different from the second slope. | 07-21-2011 |
| 20110206174 | NUCLEAR FUEL, A FUEL ELEMENT, A FUEL ASSEMBLY AND A METHOD OF MANUFACTURING A NUCLEAR FUEL - The invention refers to a nuclear fuel, a fuel element, a fuel assembly and a method of manufacturing a nuclear fuel. The nuclear fuel is adapted for use in a water cooled nuclear reactor, including light water reactors LWR, such as Boiling Water Reactors BWR and Pressure Water Reactors PWR. The nuclear fuel comprises an uranium-containing compound consisting of UN. The uranium content of the uranium-containing compound comprises less than 10% by weight of the isotope | 08-25-2011 |
| 20110222643 | CLADDING TUBE FOR NUCLEAR FUEL ROD, METHOD AND APPARATUS FOR MANUFACTURING A CLADDING TUBE - A cladding tube for nuclear fuel made from metal and including concave dimples on its external surface. A nuclear fuel assembly includes at least a plurality of nuclear fuel rods provided with such cladding tubes. | 09-15-2011 |
| 20110255651 | NUCLEAR REACTOR (ALTERNATIVES), FUEL ASSEMBLY OF SEED-BLANKET SUBASSEMBLIES FOR NUCLEAR REACTOR (ALTERNATIVES), AND FUEL ELEMENT FOR FUEL ASSEMBLY - Fuel elements are supported by fuel assemblies configured for use in land-based nuclear reactors such as the VVER-1000. The fuel elements include a kernel having a multi-lobed profile that forms spiral ribs that include fissionable material (e.g., uranium or plutonium), a central metal displacer extending along a longitudinal axis of the kernel, and a metal cladding (e.g., zirconium and/or other refractory metals) enclosing the kernel. The fuel element may be fabricated by joint extrusion of the displacer, kernel, and cladding through a die to metallurgically bond the kernel and cladding. | 10-20-2011 |
| 20110268243 | FUEL CHANNEL ARRANGED TO BE COMPRISED BY A FUEL ELEMENT FOR A FISSION REACTOR - A fuel channel ( | 11-03-2011 |
| 20120020447 | OPTIMIZED FUEL ASSEMBLY CHANNELS AND METHODS OF CREATING THE SAME - Fuel assemblies include an outer channel having a physical configuration optimized for a position of the fuel assembly within a core of a nuclear reactor. The position of the fuel assembly with respect to an employed control blade in the nuclear reactor determines if the outer channel may be thickened, reinforced, and/or fabricated of Zircaloy-4 or similar distortion-resistant material, so as to reduce or prevent distortion of the channel against the control blade, or thinned so as to increase water volume and enhance reactivity in the assembly. Reactor cores having configured fuel assemblies include fuel assemblies having different outer channels. Methods include determining operational characteristics of the fuel assembly, including likelihood of being placed directly adjacent to an employed control blade, and physically selecting or modifying the outer channel of the fuel assembly based thereon. | 01-26-2012 |
| 20120195402 | NEUTRON SOURCE ASSEMBLY - A neutron source rodlet assembly having a separate source capsule assembly that is not encapsulated within the neutron source rodlet assembly. The neutron source rodlet assembly is made up, at least in part, of a neutron source positioning rodlet assembly and the source capsule assembly configured such that assembly together is feasible at a remote site and they can be shipped separately. The source capsule assembly has outer and inner capsules with the outer capsule having a threaded stud at one end that mates with a complimentary threaded recess on the neutron source positioning rodlet assembly. The inner capsule contains a neutron source. The neutron source positioning rodlet assembly and the source capsule assembly are locked together at their interface when the threaded joint is completely tightened. A secondary neutron source material may also be encapsulated within a hollow portion of the neutron source positioning rodlet assembly. | 08-02-2012 |
| 20120321031 | NUCLEAR FUEL ROD AND METHOD OF MANUFACTURING PELLETS FOR SUCH A ROD - A new type of nuclear fuel rods. The rod cladding has an elliptical section transverse to its longitudinal direction and each nuclear fuel pellet has a truncated elliptical shape along the major axis of the cladding, the minor axis of the pellets is the same as the length of the minor axis of the cladding except for the assembly clearance j, the difference in length between the major axis of the cladding and the truncated major axis of the pellets is very much larger than the assembly clearance j. Also disclosed is a method of manufacturing nuclear fuel rods and stacking them in the cladding so as to form a nuclear fuel rod. | 12-20-2012 |
| 20130010914 | COMPOSITE MATERIALS, BODIES AND NUCLEAR FUELS INCLUDING METAL OXIDE AND SILICON CARBIDE AND METHODS OF FORMING SAME - Methods of forming composite bodies and materials including a metal oxide, such as, uranium dioxide, and silicon carbide are disclosed. The composite materials may be formed from a metal oxide powder, a silicon carbide powder and, optionally, a carbon powder. For example, the metal oxide powder, the silicon carbide powder and the carbon powder, if present, may each be combined with a binder and may be deposited in succession to form a precursor structure. Segments of the precursor structure may be removed and pressed together to form a multi-matrix material that includes interlaced regions of material including at least one of the metal oxide powder, the silicon carbide powder and, optionally, the carbon powder. The segments may be extruded or coextruded with another material, such as, a silicon carbide material, to form a green body. The green body may be sintered to form the composite bodies and materials having a desired final density. | 01-10-2013 |
| 20130329849 | METAL NUCLEAR-FUEL PIN INCLUDING A SHELL HAVING THREADS OR FIBERS MADE OF SILICON CARBIDE (SIC) - A nuclear-fuel pin including a linear element made of a metal nuclear-fuel material consisting of uranium and/or plutonium, and cladding including Fe and Cr or an alloy including at least both of said elements, comprises a main shell provided around the linear nuclear-fuel element, said shell including threads or fibers made of SiC. A method for producing a nuclear-fuel pin is also provided. | 12-12-2013 |
| 20140050293 | THERMOACOUSTIC ENHANCEMENTS FOR NUCLEAR FUEL RODS AND OTHER HIGH TEMPERATURE APPLICATIONS - A nuclear thermoacoustic device includes a housing defining an interior chamber and a portion of nuclear fuel disposed in the interior chamber. A stack is disposed in the interior chamber and has a hot end and a cold end. The stack is spaced from the portion of nuclear fuel with the hot end directed toward the portion of nuclear fuel. The stack and portion of nuclear fuel are positioned such that an acoustic standing wave is produced in the interior chamber. A frequency of the acoustic standing wave depends on a temperature in the interior chamber. | 02-20-2014 |
| 20140185730 | URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING CERAMIC MICROCELLS AND FABRICATING METHOD THEREOF - A uranium dioxide nuclear fuel pellet has about 50 to about 400 μM (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside. | 07-03-2014 |
| 20140185731 | URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING METALLIC MICROCELLS AND FABRICATING METHOD THEREOF - A uranium dioxide nuclear fuel pellet includes metallic microcells having a high protection capacity for fission products and a high thermal conductivity simultaneously arranged in the nuclear fuel pellet to trap fission products, such that extraction of fission products may be restrained in a normal operation condition and that the temperature of a nuclear fuel may be lowered to enhance the performance of the nuclear fuel, only to restrain extraction of radioactive fission products toward the environment in an accident condition to enhance a stability of the nuclear fuel pellet, and a fabricating method thereof. | 07-03-2014 |
| 20140294135 | POWDER OF AN ALLOY BASED ON URANIUM AND MOLYBDENUM IN GAMMA-METASTABLE PHASE, COMPOSITION OF POWDERS COMPRISING THIS POWDER, AND USES OF SAID POWDER AND COMPOSITION - The invention relates to a powder of an alloy comprising uranium and molybdenum in γ-metastable phase, a composition of powders comprising this powder, and the uses of said alloy powder and of said composition of powders. | 10-02-2014 |
| 20140307844 | Fuel rods having irradiation target end pieces - Example embodiments are directed to a fuel rod having end pieces on either end containing irradiation targets. Example embodiment end pieces may contain materials that may be converted to desired isotopes when exposed to neutron flux encountered at the end piece position. Example embodiment end pieces may be fabricated from the materials or may otherwise house the materials. Example embodiment end pieces may mate with a variety of full-length and/or part-length fuel rods and may function as upper and/or lower end plugs, mating the fuel rods to upper and/or lower tie plates. | 10-16-2014 |
| 20150310940 | NUCLEAR FUEL ELEMENT - A top end plug design for a nuclear fuel rod or control rod that maximizes the fuel rod length and internal volume for high burn-up, but limits plenum spring melting for eutectic formation margin. The press fit length of the top end plug is increased to increase the distance from the center of heat from the TIG welding process that seals the end plug to the cladding, to the back face of the end plug. A hole in the back of the end plug is enlarged to recover the volume loss from the press fit length increase. | 10-29-2015 |
| 376414000 | Coated, preformed, or impregnated layer or part or adhesively bonded layers or parts | 39 |
| 20090252279 | Fuel Pellet for a Nuclear Reactor and Method for Producing Fuel Pellet - A fuel pellet for a nuclear reactor contains a matrix made of an oxidic nuclear fuel and a metallic phase that is deposited within or between the fuel grains and is preferably aligned in a radial direction relative to the coating surface of the pellet. A method for producing the fuel pellet includes forming slugs containing a precursor of the metallic phase, which has a melting point lying below the sintering temperature and can be transformed into the metallic phase in sintering conditions, in addition to the oxidic nuclear fuel and other optional additives. The slugs are then sintered. The slugs are heated up so quickly that at least one portion of the precursor is liquefied before being completely transformed into the metallic phase. | 10-08-2009 |
| 20100091933 | METHOD OF PRODUCING LARGE-GRAINED NUCLEAR FUEL PELLET BY CONTROLLING CHROME CATION SOLUBILITY IN UO2 LATTICE - In a method of producing large-grained nuclear fuel pellet, Cr-compound contained in an uranium oxide green pellet is reduced to Cr phase at 1,470° C. or below and maintained to the Cr phase, and the uranium oxide green pellet containing the Cr-compound is then sintered at 1,650° C.-1,800° C. in a gas atmosphere of oxygen potential at which Cr element in the uranium oxide green pellet becomes liquid phase. | 04-15-2010 |
| 20120114091 | ZIRCONIUM ALLOY MATERIAL - Disclosed is a zirconium alloy material having high corrosion resistance regardless of thermal history during its manufacturing process. The zirconium alloy material is obtained by providing a zirconium alloy containing on the mass basis: 0.001% to 1.9% of Sn, 0.01% to 0.3% of Fe, 0.01% to 0.3% of Cr, 0.001% to 0.3% of Ni, 0.001% to 3.0% of Nb, 0.027% or less of C, 0.025% or less of N, 4.5% or less of Hf and 0.16% or less of O with the remainder being inevitable impurities and zirconium, being formed of a bulk alloy and a surface layer, in which the surface layer has a plastic strain of 3 or more or a Vickers hardness of 260 HV or more and an arithmetic mean surface roughness Ra of 0.2 μm or less. | 05-10-2012 |
| 20120140867 | FULLY CERAMIC NUCLEAR FUEL AND RELATED METHODS - Various embodiments of a nuclear fuel for use in various types of nuclear reactors and/or waste disposal systems are disclosed. One exemplary embodiment of a nuclear fuel may include a fuel element having a plurality of tristructural-isotropic fuel particles embedded in a silicon carbide matrix. An exemplary method of manufacturing a nuclear fuel is also disclosed. The method may include providing a plurality of tristructural-isotropic fuel particles, mixing the plurality of tristructural-isotropic fuel particles with silicon carbide powder to form a precursor mixture, and compacting the precursor mixture at a predetermined pressure and temperature. | 06-07-2012 |
| 20120207264 | COATED NUCLEAR REACTOR FUEL PARTICLES - A method is described for producing nuclear fuel products, including the steps of receiving metallic or intermetallic uranium-based fuel particle cores, providing at least one physical vapour deposited coating layer surrounding the fuel particle core and embedding the nuclear fuel particles in a matrix so as to form a powder mixture of matrix material and coated fuel particles. The at least one physical vapour deposited coating layer may include inhibitors of inhibiting, stabilizing and/or reducing interaction between metallic and intermetallic uranium-based fuel particles cores and the matrix wherein the fuel particles typically may be embedded. The deposited coating layer may include neutron poisons. | 08-16-2012 |
| 20130251087 | SURFACE MODIFICATION OF CLADDING MATERIAL - Provided in one embodiment is a method comprising: disposing atoms of at least one non-metal element over a surface of a cladding material of a nuclear fuel element; and forming at least one product comprising the at least one non-metal element in, over, or both, a surface layer of the cladding material; wherein the at least one non-metal element has an electronegativity that is smaller than or equal to that of oxygen. Also provided is a nuclear fuel element comprising a modified surface layer adapted to mitigate formation of Chalk River Unidentified Deposits (CRUD) on the cladding material. | 09-26-2013 |
| 20140205054 | NUCLEAR FUEL ROD FOR FAST REACTORS INCLUDING METALLIC FUEL SLUG COATED WITH PROTECTIVE COATING LAYER AND FABRICATION METHOD THEREOF - Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors. | 07-24-2014 |
| 20140241485 | Unknown - A nuclear fuel cladding tube for a liquid-metal or molten-salt cooled reactor includes a tubular body of metal material and a protective coating applied on an outer surface of the tubular body, to contact the coolant. The coating includes at least one layer of coating material selected from the group consisting of ceramic materials, refractory metals, and FeCrAlY alloys, and includes a matrix composed of the coating material in amorphous phase, inside which nanodomains composed of the coating material in crystalline phase are dispersed. | 08-28-2014 |
| 20150063521 | DESIGNED POROSITY MATERIALS IN NUCLEAR REACTOR COMPONENTS - A nuclear fuel pellet with a porous substrate, such as a carbon or tungsten aerogel, on which at least one layer of a fuel containing material is deposited via atomic layer deposition, and wherein the layer deposition is controlled to prevent agglomeration of defects. Further, a method of fabricating a nuclear fuel pellet, wherein the method features the steps of selecting a porous substrate, depositing at least one layer of a fuel containing material, and terminating the deposition when the desired porosity is achieved. Also provided is a nuclear reactor fuel cladding made of a porous substrate, such as silicon carbide aerogel or silicon carbide cloth, upon which layers of silicon carbide are deposited. | 03-05-2015 |
| 376416000 | Multiple or composite cladding-type layers | 30 |
| 20080240334 | FUEL ELEMENTS FOR NUCLEAR REACTOR SYSTEM - A fuel element for nuclear power generation made up of at least one coated UO | 10-02-2008 |
| 20080310578 | Pressurizer Heater for the Primary Cooling System of a Pressurized-Water Nuclear Reactor - The invention relates to a heating rod for a pressurizer of a primary cooling system of a pressurized-water nuclear reactor, the rod comprising a metal outer shell ( | 12-18-2008 |
| 20090022259 | FUEL ROD WITH WEAR-INHIBITING COATING - A fuel rod includes a cladding tube with a wear-inhibiting coating. In one embodiment, the coating is made of a metallic powder material that is applied to the exterior surface of the cladding tube using a thermal spray process. In an alternative embodiment, the coating is a composite made of a metallic powder material, and a ceramic powder material or a metal oxide hard phase powder material that is simultaneously applied with the metallic powder material to coat the cladding tube. The coating can be applied to selected areas of the fuel rods where debris tends to fret the fuel rod. | 01-22-2009 |
| 20090046826 | Fuel Cladding Protective Sleeve, Method for Producing Fuel Rods and Device for Carrying out Said Method - Method for producing fuel rods characterized in that it comprises the steps of:
| 02-19-2009 |
| 20090060116 | FUEL ROD OF NUCLEAR FUEL ASSEMBLY HAVING VASE-LIKE COMPRESSION SPRING ADAPTED TO INCREASE INTERNAL VOLUME THEREOF - The present invention relates to a fuel rod of a nuclear fuel assembly having a vase-like compression spring adapted to increase the internal volume thereof wherein when the vase-like compression spring is inserted into a cladding tube, it has a relatively smaller volume occupied inside the fuel rod when compared with the existing coil type compression spring, such that the vase-like compression spring can ensure a sufficient space portion receiving the fission gases generated during the operation of the fuel rod, thereby increasing the burn-up performance of the fuel rod and the mechanical integrity thereof. | 03-05-2009 |
| 20090220040 | TUBULAR BODY AND METHOD FOR PRODUCING THE SAME - A tubular body includes a tubular fiber-reinforced carbonaceous substrate and an SiC layer. The tubular fiber-reinforced carbonaceous substrate includes an aggregate formed of ceramic fibers, and a carbonaceous material filled in interstices between the ceramic fibers. The SiC layer is formed at least on an outer surface of the tubular fiber-reinforced carbonaceous substrate in which silicon atoms are diffused from a boundary region between the fiber-reinforced carbonaceous substrate and the SiC layer to an inside of the fiber-reinforced carbonaceous substrate. | 09-03-2009 |
| 20100091934 | FUEL ROD ASSEMBLY AND METHOD FOR MITIGATING THE RADIATION-ENHANCED CORROSION OF A ZIRCONIUM-BASED COMPONENT - There is provided a fuel rod assembly comprising a first component of a zirconium-based material. The first component is in contact with or is located adjacent to a second component of a material different from the zirconium-based material, e.g. a nickel-based or iron-based alloy. A coating is disposed on an outer surface of the first component, which is effective to reduce an electrochemical corrosion potential difference between the first component and the second component relative to an electrochemical corrosion potential difference between the first component and the second component without the coating. | 04-15-2010 |
| 20100226472 | NUCLEAR FUEL ELEMENT AND ASSEMBLY - A nuclear fuel element having a thick walled lower section that transitions to a thinner walled upper section with the transition forming an annular interior ledge that supports the fuel pellets spaced above a bottom end plug. The space between the fuel pellets and the bottom end plug forms a gas collection plenum that assures the necessary void volume exists to maintain margin to rod internal pressure limits. | 09-09-2010 |
| 20100266094 | DUAL-COOLED NUCLEAR FUEL ROD HAVING ANNULAR PLUGS AND METHOD OF MANUFACTURING THE SAME - A dual-cooled nuclear fuel rod and a method of manufacturing the same are provided. The nuclear fuel rod includes an outer cladding tube having a circular cross section, an inner cladding tube having an outer diameter smaller than an inner diameter of the outer cladding tube, and a length longer than the outer cladding tube, and located in parallel in the outer cladding tube, a pellet charged in a space between the outer and inner cladding tubes and generating energy by nuclear fission, and first and second end plugs coupling opposite ends of the outer cladding tube to stepped outer joints formed on outer circumferences of first ends thereof and coupling opposite ends of the inner cladding tube to stepped inner joints formed on inner circumferences of the first ends thereof. | 10-21-2010 |
| 20110002433 | Water Reactor Fuel Cladding Tube - A water reactor fuel cladding tube ( | 01-06-2011 |
| 20110170653 | NUCLEAR FUEL CLADDING WITH HIGH HEAT CONDUCTIVITY AND METHOD FOR MAKING SAME - The invention relates to a nuclear fuel cladding totally or partially made of a composite material with a ceramic matrix containing silicon carbide (SiC) fibers as a matrix reinforcement and an interphase layer provided between said matrix and said fibers, the matrix including at least one carbide selected from titanium carbide (TiC), zirconium carbide (ZrC), or ternary titanium silicon carbide (Ti | 07-14-2011 |
| 20110194666 | SHEATHED, ANNULAR METAL NUCLEAR FUEL - A sheathed, annular metal fuel system is described. A metal fuel pin system is described that includes an annular metal nuclear fuel alloy. A sheath may surround the metal nuclear fuel alloy, and a cladding may surround the sheath. A gas plenum may also be present. Mold arrangements and methods of fabrication of the sheathed, annular metal fuel are also described. | 08-11-2011 |
| 20110286570 | SOLID HOLLOW CORE FUEL FOR FUSION-FISSION ENGINE - A fuel pebble for use in a fusion-fission engine includes a buffer material and a fertile or fissile fuel shell surrounding the buffer material. The fuel pebble also includes a containment shell surrounding the fertile or fissile fuel shell. The containment shell includes silicon carbide. The fuel pebble further includes a composite material layer surrounding the containment shell and a cladding layer surrounding the composite material layer. | 11-24-2011 |
| 20120087457 | CLADDING MATERIAL, TUBE INCLUDING SUCH CLADDING MATERIAL AND METHODS OF FORMING THE SAME - A multi-layered cladding material including a ceramic matrix composite and a metallic material, and a tube formed from the cladding material. The metallic material forms an inner liner of the tube and enables hermetic sealing of thereof. The metallic material at ends of the tube may be exposed and have an increased thickness enabling end cap welding. The metallic material may, optionally, be formed to infiltrate voids in the ceramic matrix composite, the ceramic matrix composite encapsulated by the metallic material. The ceramic matrix composite includes a fiber reinforcement and provides increased mechanical strength, stiffness, thermal shock resistance and high temperature load capacity to the metallic material of the inner liner. The tube may be used as a containment vessel for nuclear fuel used in a nuclear power plant or other reactor. Methods for forming the tube comprising the ceramic matrix composite and the metallic material are also disclosed. | 04-12-2012 |
| 20130170603 | NUCLEAR FUEL ROD FOR FAST REACTOR - A nuclear fuel rod for a fast reactor includes tubular fuel materials comprising a hollow portion formed therein, a tubular inner pipe inserted into the hollow portion of the tubular fuel materials to prevent collapse of the tubular fuel materials due to combustion of nuclear fuel, a tubular cladding pipe which surrounds the tubular fuel materials, and a liquid metal, or He gas or vacuum applied in a gap between the tubular fuel materials and the tubular cladding pipe. | 07-04-2013 |
| 20140126683 | DEPOSITION OF INTEGRATED PROTECTIVE MATERIAL INTO ZIRCONIUM CLADDING FOR NUCLEAR REACTORS BY HIGH-VELOCITY THERMAL APPLICATION - A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface ( | 05-08-2014 |
| 20140185732 | METHOD AND APPARATUS FOR A FRET RESISTANT FUEL ROD FOR A LIGHT WATER REACTOR (LWR) NUCLEAR FUEL BUNDLE - A method and apparatus for a fret resistant fuel rod for a Boiling Water Reactor (BWR) nuclear fuel bundle. An applied material entrained with fret resistant particles is melted or otherwise fused to a melted, thin layer of the fuel rod cladding. The applied material is made of a material that is chemically compatible with the fuel rod cladding, allowing the fret resistant particles to be captured in the thin layer of re-solidified cladding material to produce an effective and resilient fret resistant layer on an outer layer of the cladding. | 07-03-2014 |
| 20150063522 | Fuel Rod Cladding and Methods for Making and Using Same - In general, the present invention is directed to novel nuclear fuel rod claddings that have better performance characteristics compared to current claddings, particularly during a severe accident, such as a loss of coolant accident. The present invention provides a duplex cladding having two layers, an inner Mo or Mo-alloy layer and a protective layer disposed on the outside of the Mo or Mo-alloy layer. Optionally, the Mo or Mo-alloy layer may have a coating disposed on its inner surface to provide additional capability with the fuel pellets, thereby creating a triplex cladding. | 03-05-2015 |
| 20150063523 | COATING OF NUCLEAR FUEL CLADDING MATERIALS, METHOD FOR COATING NUCLEAR FUEL CLADDING MATERIALS - The invention provides a nuclear reactor cladding, wherein at least one layer of coating is deposited on the exterior surface of the cladding. A nuclear reactor cladding, wherein at least one layer of coating is deposited on the interior surface of the cladding. A method of coating a nuclear reactor cladding, with the steps of selecting the cladding and depositing at least one layer of a first coating on the cladding. | 03-05-2015 |
| 20150098545 | Deposition of Integrated Protective Material Into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application - A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface ( | 04-09-2015 |
| 20150318062 | Structure, Electronic Element Module, Heat Exchanger, Fuel Rod, and Fuel Assembly - Provided is a structure including a first member ( | 11-05-2015 |
| 20160049211 | SILICON CARBIDE MULTILAYERED CLADDING AND NUCLEAR REACTOR FUEL ELEMENT FOR USE IN WATER-COOLED NUCLEAR POWER REACTORS - A nuclear fuel element for use in water-cooled nuclear power reactors and an improved multilayered silicon carbide tube for use in water-cooled nuclear power reactors and other high temperature, high strength thermal tubing applications including solar energy collectors. The fuel element includes a multilayered silicon carbide cladding tube. The multilayered silicon carbide cladding tube includes (i) an inner layer; (ii) a central layer; and (iii) a crack propagation prevention layer between the inner layer and the central layer. A stack of individual fissionable fuel pellets may be located within the cladding tube. In addition, a thermally conductive layer may be deposited within the cladding tube between the inner layer of the cladding tube and the stack of fuel pellets. The multilayered silicon carbide cladding tube may also be adapted for other high temperature, high strength thermal tubing applications including solar energy collectors. | 02-18-2016 |
| 20180025797 | METHODS OF FORMING STRUCTURES AND FISSILE FUEL MATERIALS BY ADDITIVE MANUFACTURING AND RELATED STRUCTURES | 01-25-2018 |
| 376417000 | Including getter layer or barrier layer | 7 |
| 20090141851 | NUCLEAR FUEL ROD FOR FAST REACTORS WITH OXIDE COATING LAYER ON INNER SURFACE OF CLADDING, AND MANUFACTURING METHOD THEREOF - Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way. | 06-04-2009 |
| 20100054389 | MIXED OXIDE FUEL ASSEMBLY - A pressurized water nuclear reactor fuel assembly designed to burn mixed oxide fuel that employs a fully annular fuel pellet stack in the fuel rods, and radial enrichment zoning within the assembly such that the intra-assembly rod power distribution is relatively smooth regardless of the characteristics of the adjacent assemblies. | 03-04-2010 |
| 20130010915 | REACTOR FUEL ELEMENTS AND RELATED METHODS - Fuel elements for use in reactors include a cladding tube having a longitudinal axis and fuel disposed therein. At least one channel is formed in at least one of the fuel and the cladding tube and extends in a direction along the longitudinal axis of the cladding tube. The fuel element further includes a plenum having at least one getter material disposed therein. Methods of segregating gases in fuel elements may include forming a temperature differential in the fuel element, enabling at least one gas to travel into at least one channel formed in the fuel element, and retaining a portion of the at least one gas with at least one getter material. Methods of segregating gases in fuel elements also may include enabling at least one gas to travel through at least one channel of a plurality of channels formed in the fuel element. | 01-10-2013 |
| 20130077731 | CERAMIC ENCAPSULATIONS FOR NUCLEAR MATERIALS AND SYSTEMS AND METHODS OF PRODUCTION AND USE - A novel containment system for encapsulating nuclear fuel particles is disclosed. The containment system has a gas-impervious ceramic composite hollow shell having a spheroidal or ovoidal shape. The shell has a pair of longitudinally aligned round openings that are sealed with a gas-impervious ceramic composite tube to define a cavity between the shell inner surface and the tube outer surface. A ceramic composite matrix containing the nuclear fuel particles is enclosed within the cavity. The ceramic composite matrix has a controlled porosity, and can contain moderators or neutron absorbing material. The tube and shell are composed of a ceramic matrix composite material composed of ceramic reinforcement material that is bound together by a polymer-derived ceramic material. | 03-28-2013 |
| 20140185733 | NUCLEAR FUEL ELEMENT - Disclosed embodiments include fuel assemblies, methods of making a fuel element, and methods of using a fuel element. | 07-03-2014 |
| 20140254740 | FUEL RODS WITH WEAR-INHIBITING COATINGS AND METHODS OF MAKING THE SAME - Nuclear reactor components are treated with thermal methods to increase wear resistance. Example treatments include thermal treatments using particulate or powderized materials to form a coating. Methods can use cold spray, with low heat and high velocities to blast particles on the surface. The particles impact and mechanically deform, forming an interlocking coating with the surface and each other without melting or chemically reacting. Materials in the particles and resultant coatings include metallic alloys, ceramics, and/or metal oxides. Nuclear reactor components usable with methods of increased wear resistance include nuclear fuel rods and assemblies containing the same. Coatings may be formed on any desired surface, including fuel rod positions where spacer contact and fretting is most likely. | 09-11-2014 |
| 20150063524 | ALD COATING OF NUCLEAR FUEL ACTINIDES MATERIALS - A method of forming a nuclear fuel pellet, with the steps of obtaining a fuel form in a powdered state; coating the fuel form in a powdered state with at least one layer of a material; and sintering the powdered fuel form into a fuel pellet. A sintered nuclear fuel pellet, wherein the pellet is made from a powdered fuel form, wherein the powdered fuel form is coated with at least one layer of a material, and wherein the at least one layer of the material substantially surrounds each interfacial grain barrier after the powdered fuel form has been sintered. | 03-05-2015 |
| 376418000 | Getter, fission product retainer of filter | 1 |
| 20110194667 | DOPANTS FOR HIGH BURNUP IN METALLIC NUCLEAR FUELS - A binary or ternary metallic fuel composition having a metal dopant content of about 1 at. % to 25 at. %. A metal dopant is added to the binary or ternary metallic fuel composition to extend metal fuel burnup. The metal dopant will pin the lanthanides in the fuel phases. For binary U—Zr fuels, the metal dopant is generally palladium or titanium. For ternary U—Pu—Zr fuels, the metal dopant is generally palladium or a mixture of silver and titanium. | 08-11-2011 |
| 376419000 | Burnable poison | 12 |
| 20090028284 | METHOD OF CONTROLLING CRITICALITY OF NUCLEAR FUEL CYCLE FACILITY, METHOD OF PRODUCING URANIUM DIOXIDE POWDER, REACTOR FUEL ROD, AND FUEL ASSEMBLY - A method of controlling the criticality of a nuclear fuel cycle facility includes steps of producing a reactor fuel by adding less than 0.1% by weight of gadolinia to a uranium dioxide powder with a uranium enrichment of greater than 5% by weight and controlling the effective neutron multiplication factor of a uranium dioxide system in a step of handling the reactor fuel to be less than or equal to the maximum of the effective neutron multiplication factor of a uranium dioxide system with a uranium enrichment of 5% by weight. | 01-29-2009 |
| 20100040189 | ERBIUM-CONTAINING ZIRCONIUM ALLOY, METHODS FOR PREPARING AND SHAPING THE SAME, AND STRUCTURAL COMPONENT CONTAINING SAID ALLOY. - A zirconium alloy, comprising erbium as a burnable neutron poison, said alloy comprising, by weight:
| 02-18-2010 |
| 20100266095 | Burnable Poison Materials and Apparatuses for Nuclear Reactors and Methods of Using the Same - Example embodiments are directed to materials useable as burnable poisons in nuclear reactors, components using the same, and methods of using the same. Example embodiment burnable poison materials produce desired daughter products as they burn out, thereby permitting placement and use for neutronic characteristic improvement and/or neutron flux shielding in locations conventionally barred as uneconomical. Example embodiment burnable poison materials may include natural iridium and enriched iridium-193. Example embodiment components may be fabricated, shaped, and placed to provide desired burnable poison effects in the reactor core in conventional locations and locations not conventionally used due to economic infeasibility. Example methods include use of example embodiment components, including determining locations benefiting from burnable poison effects, fabricating example embodiment components of a desired amount of example embodiment burnable poison materials, placing the example embodiment components, exposing example embodiment components to flux within the operating nuclear reactor, removing and harvesting example embodiment burnable poison components for desired daughter products produced from example embodiment burnable poison materials. | 10-21-2010 |
| 20110002434 | METHOD OF APPLYING A BURNABLE POISON ONTO THE EXTERIOR OF NUCLEAR FUEL ROD CLADDING - An article made by applying a burnable poison onto the cladding of a nuclear fuel rod, which involves providing a nuclear fuel rod and at least one application device, rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod by spraying an abrasive material onto the nuclear fuel rod via the application device while adjusting the position of the application device in relation to the nuclear fuel rod, and applying burnable poison particles onto the outer surface of the nuclear fuel rod by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device in relation to the nuclear fuel rod, where the burnable poison particles are applied at a velocity sufficient to cause adhesion to the outer surface of the cladding. | 01-06-2011 |
| 20110249785 | EXPOSURE BOOST ZONE FOR BOILING WATER REACTOR NUCLEAR BUNDLES - Disclosed are a fuel rod and a fuel bundle using the fuel rod. The fuel rod may include first enriched uranium in a boost zone of the fuel rod, wherein the boost zone may be arranged directly at a bottom of the fuel rod. The fuel rod may also include second enriched uranium in a second zone of the fuel rod, wherein the second zone is arranged over the boost zone. The fuel rod may also include natural uranium in a third zone of the fuel rod, wherein the third zone is arranged over the second zone. In this fuel rod, a percent of enrichment of the enriched uranium in the boost zone is at least one percent. | 10-13-2011 |
| 20120140868 | FUEL ROD AND FUEL ASSEMBLY - [Problem to be Solved] To provide a fuel rod and a fuel assembly that can make thermal power uniform along an axial direction and lengthen an operation cycle. | 06-07-2012 |
| 20130114781 | FULLY CERAMIC MICROENCAPSULATED REPLACEMENT FUEL ASSEMBLIES FOR LIGHT WATER REACTORS - A fully ceramic micro-encapsulated fuel assembly for a light water nuclear reactor includes a set of FCM fuel rods bundled in a square matrix arrangement. Fully ceramic micro-encapsulated fuel assemblies replace standard reference solid fuel assemblies with smaller number of FCM fuel rods that have a larger diameter than the diameter of the solid standard reference fuel rods, while keeping similar amounts of fissile material in the fuel assembly and maintaining comparable rates of burnup and number of EFPDs, and compatible power production, heat transfer and thermo-hydraulic features. A fully ceramic micro-encapsulated fuel rod includes multiple fully ceramic micro-encapsulated fuel pellets, which are comprised of tristructural-isotropic particles. In order to obtain compatible burnup rates with the standard reference fuel, the tristructural-isotropic particles have preferentially large diameter and packing fraction. Furthermore, Erbium oxide is included in the sintered mix of the SiC compact to serve as a burnable poison. | 05-09-2013 |
| 20130223582 | FABRICATION METHOD OF BURNABLE ABSORBER NUCLEAR FUEL PELLETS AND BURNABLE ABSORBER NUCLEAR FUEL PELLETS FABRICATED BY THE SAME - A fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same are provided, in which the fabrication method includes adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO | 08-29-2013 |
| 20130266112 | NUCLEAR FUEL CONTAINING RECYCLED AND DEPLETED URANIUM, AND NUCLEAR FUEL BUNDLE AND NUCLEAR REACTOR COMPRISING SAME - Nuclear fuels for nuclear reactors are described, and include nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of depleted uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2 wt % of | 10-10-2013 |
| 20130322590 | EXTENSION OF METHODS TO UTILIZE FULLY CERAMIC MICRO-ENCAPSULATED FUEL IN LIGHT WATER REACTORS - A 12×12 fully ceramic micro-encapsulated fuel assembly for a light water nuclear reactor includes a set of FCM fuel rods bundled in a square matrix arrangement. The fully ceramic micro-encapsulated fuel is comprised of tristructural-isotropic particles. Each tristructural-isotropic particle has a kernel that is comprised uranium nitride. The kernel diameter is 400 or more micrometers. The fully ceramic micro-encapsulated fuel is further mixed with a burnable poison material. | 12-05-2013 |
| 20140334595 | FUEL ASSEMBLY - Nuclear fuel assemblies include non-symmetrical fuel elements with reduced lateral dimensions on their outer lateral sides that facilitate fitting the fuel assembly into the predefined envelope size and guide tube position and pattern of a conventional nuclear reactor. Nuclear fuel assemblies alternatively comprise a mixed grid pattern that positions generally similar fuel elements in a compact arrangement that facilitates fitting of the assembly into the conventional nuclear reactor. | 11-13-2014 |
| 20160104548 | NOVEL MATERIAL MADE OF URANIUM, GADOLINIUM AND OXYGEN AND USE THEREOF AS CONSUMABLE NEUTRON POISON - The present invention relates to a novel material made of uranium, gadolinium and oxygen, having a crystalline phase having cubic crystallographic structure, having an atomic ratio Gd/[Gd+U] of 0.6 to 0.93, the uranium being present in an oxidation state of +IV and/or +V. The invention further relates to the use of such a material as a consumable neutron poison of a fuel element. | 04-14-2016 |
| 376420000 | Interpellet spacing or positioning means | 1 |
| 20090041175 | Fuel Element for Pressurised Water Nuclear Reactors and Method of Loading Fuel Elements Into a Nuclear Reactor Core - The invention relates to a fuel assembly for pressurised water nuclear reactors comprising a plurality of nuclear fuel rods each of which comprises a plurality of pellets with nuclear fuel. The assembly includes both pellets with high-concentration gadolinium oxide (greater or equal to 6% by weight) and pellets with medium-concentration gadolinium oxide (greater than 2% by weight and less than or equal to 4% by weight). | 02-12-2009 |
| 376421000 | Homogeneously intermixed | 1 |
| 20110293061 | Liquid fuel nuclear fission reactor - Disclosed embodiments include nuclear fission reactors, nuclear fission fuel pins, methods of operating a nuclear fission reactor, methods of fueling a nuclear fission reactor, and methods of fabricating a nuclear fission fuel pin. | 12-01-2011 |
| 376423000 | Moderator or reflector | 3 |
| 20100034336 | CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY - A core of a light water reactor having a plurality of fuel assemblies, which are loaded in said core, having nuclear fuel material containing a plurality of isotopes of transuranium nuclides, an upper blanket zone, a lower blanket zone, and a fissile zone, in which the transuranium nuclides are contained, disposed between the upper blanket zone and the lower blanket zone;
| 02-11-2010 |
| 20110317800 | NUCLEAR FUEL - A nuclear fuel composition includes a nuclear fissile material and a neutron-absorption material that adjoins the nuclear fissile material. The nuclear fuel composition may be used in a nuclear reactor, such as a thermal reactor. | 12-29-2011 |
| 20160099081 | MODERATING FUEL RODS INCLUDING METAL HYDRIDE AND METHODS OF MODERATING FUEL BUNDLES OF BOILING WATER REACTORS USING THE SAME - A moderating fuel rod for a boiling water reactor may include a nuclear fuel section; a neutron moderator section including a metal hydride; and a threaded connector joining the nuclear fuel section and the neutron moderator section. By including one or more moderating fuel rods in a fuel bundle, the neutron moderation within the fuel bundle may be improved, thereby allowing energy to be more efficiently extracted from the entire length of the fuel bundle. | 04-07-2016 |
| 376424000 | Coolant or heat exchange material | 1 |
| 20100040190 | Tubular Reactor With Expandable Insert - A tubular reactor having an insert for improving heat transfer characteristics of the tubular reactor. The insert comprises a catalyst and metal structures consecutively arranged in a lengthwise direction of the tube. The metal structures have radially expandable side walls and orifices for squeezing fluid between the metal structures and the tube wall. The radially expandable side walls form hollows between the radially expandable side walls and the tube wall of the tubular reactor. The radially expandable side walls deform responsive to the fluid pressure difference between the inside of the metal structure and the outer space between the metal structure and the tube wall thereby maintaining the gap between the orifice opening and the tube wall to adjust for tube creep. | 02-18-2010 |
