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US20150054184 Granulation of Fine Powder  
A mixture of fine powder including thorium oxide was converted to granulated powder by forming a first-green-body and heat treating the first-green-body at a high temperature to strengthen the...
US20120098149 METHOD OF CONTROLLING SOLUBILITY OF ADDITIVES AT AND NEAR GRAIN BOUNDARIES, AND METHOD OF MANUFACTURING SINTERED NUCLEAR FUEL PELLET HAVING LARGE GRAIN SIZE USING THE SAME  
Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the...
US20130148774 POROUS UO2 SINTERED PELLETS AND METHOD FOR FABRICATING POROUS UO2 SINTERED PELLETS AND ELECTROLYTIC REDUCTION USING SAME  
A method for fabricating porous UO2 sintered pellets to be fed into the electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a...
US20140064434 SPACERS WITH DEFLECTION-LIMITED ROD CONTACTS FOR NUCLEAR FUEL ASSEMBLIES AND METHODS OF MAKING THE SAME  
Nuclear fuel spacers include a deflection-limited elastic rod contact. Spacers may additionally include a rigid contact without elastic functionality. A degree of deflection may be chosen based on...
US20110100439 RADIOISOTOPE POWER SOURCE  
A radioisotope power sources that includes radioisotope nanoparticles and scintillator materials. An embodiment of the radioisotope power source includes radioisotope nanoparticles suspended...
US20140185730 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...
US20110169178 METHOD FOR PREPARING A MIXED FUEL COMPRISING URANIUM AND AT LEAST ONE ACTINIDE AND/OR LANTHANIDE APPLYING A CATION EXCHANGE RESIN  
The invention relates to a method for preparing a fuel based on oxide, carbide, and/or oxycarbide comprising uranium and at least one actinide and/or lanthanide component, comprising the following...
US20110121473 Method for Fabricating Sintered Annular Nuclear Fuel Pellet Through Rod-Inserted Sintering  
A method for fabricating a sintered annular nuclear fuel pellet includes: molding nuclear fuel powder or granules to fabricate an annular nuclear fuel green body; inserting a rod-like shaped...
US20130284634 SINTER BONDED CONTAINMENT TUBE  
A containment tube includes a sealed tube comprising silicon carbide, first and second ends, an inner bore extending along at least a portion of its axial length between the first and second ends,...
US20130240805 Uranium Dioxide Nuclear Fuel Containing Mn and Al as Additives and Method of Fabricating the Same  
UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.
US20120228788 METHOD FOR PREPARING A POROUS NUCLEAR FUEL BASED ON AT LEAST ONE MINOR ACTINIDE  
A method for manufacturing a porous fuel comprising uranium, optionally plutonium and at least one minor actinide is provided. The method may comprise the following successive steps: a) a step for...
US20150170767 FULLY CERAMIC MICRO-ENCAPSULATED (FCM) FUEL FOR CANDUs AND OTHER REACTORS  
A fuel pellet for a nuclear reactor includes a plurality of tristructural-isotropic fuel particles embedded in a structural silicon carbide matrix. A method of manufacturing a fuel pellet includes...
US20130308736 Porous Scaffolds for Hydrogen Fuel in Inertial Confinement Fusion Capsules  
A fusion fuel capsule is disclosed having a substantially spherical ablator shell. The interior surface of the shell is lined with a nanoporous scaffold layer wetted with either a fully or...
US20140198485 APPARATUS AND METHOD FOR ENCAPSULATING TRITIUM  
A module comprising: one or more vials containing tritium; one or more tritium covers; and an open space within the one or more tritium covers, wherein the one or more vials containing tritium are...
US20130223582 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...
US20120321031 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...
US20120183116 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...
US20110293061 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...
US20120257707 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...
US20140350326 Brachytherapy Seed with Fast Dissolving Matrix for Optimal Delivery of Radionuclides to Cancer Tissue  
A system, method and device for treating tumor cells utilizing a resorbable therapy seed made up of microspheres containing a beta- or alpha-particle-emitting radiation source and a resorbable...
US20130175719 Method For Fabricating Porous UO2 Sintered Pellet For Electrolytic Reduction Process For Recovering Metallic Nuclear Fuel Using Continuous Process Of Atmospheric Sintering And Reduction, And Porous UO2 Sintered Pellet Fabricated By The Same  
A method for fabricating porous UO2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a powder...
US20150221398 HIGH DENSITY U02 AND HIGH THERMAL CONDUCTIVITY UO2 COMPOSITES BY SPARK PLASMA SINTERING (SPS)  
Embodiments of the invention are directed to a method for production of a nuclear fuel pellet by spark plasma sintering (SPS), wherein a fuel pellet with more than 80% TD or more than 90% TD is...
US20120175526 IONIZATION GENERATING TUBE AND AN IONIZATION GENERATING DEVICE COMPRISING THE SAME  
This invention relates to an ionization tube and an ionization device including the same. The ionization tube according to one aspect of this invention has a hollow structure, and the tube is...
US20140197557 METHOD FOR PREPARING A POROUS NUCLEAR FUEL  
A method for producing a porous fuel including uranium, optionally plutonium, and optionally at least one minor actinide, the method including: a) compacting a mixture including a first type of...
US20110285040 METHOD AND ARRANGEMENT FOR PRODUCING FUEL CORES  
A method and an arrangement for producing spherical fuel cores and/or breeder material cores by dripping a pouring solution containing uranyl nitrate and a solution containing at least one...
US20130264726 Nitride Nuclear Fuel and Method for Its Production  
The invention relates to a nitride nuclear fuel characterized in that the nitride fuel is a pellet of a material with a single-phase solid solution of elements comprising at least a nitride of...
US20110049734 Method for Preparing Sintered Annular Nuclear Fuel Pellet  
A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body....
US20110080987 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...
US20100150300 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...
US20090035579 Solid particles, method and device for the production thereof  
The invention relates to solid particles and to a method for the production thereof from a flowable starting material and a solid part, wherein the flowable starting material is split into...
US20070260477 Method for manufacturing a solid uniform flood source for quality control of gamma imaging cameras  
A method of supplying a made-to-order flood source includes, in response to receiving an order for a flood source from a customer, selecting a mold from a plurality of molds to meet a size of the...
US20120136241 Multi-Modality Nanoparticles Having Optically Responsive Shape  
In certain embodiments novel nanoparticles (nanowontons) are provided that are suitable for multimodal imaging and/or therapy. In one embodiment, the nanoparticles include a first biocompatible...
US20140070434 IONIC LIQUIDS AS TEMPLATING AGENTS IN FORMATION OF URANIUM-CONTAINING NANOMATERIALS  
A method for forming nanoparticles containing uranium oxide is described. The method includes combining a uranium-containing feedstock with an ionic liquid to form a mixture and holding the...
US20120140867 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...
US20140183765 CERAMIC-CERAMIC COMPOSITES AND PROCESS THEREFOR, NUCLEAR FUELS FORMED THEREBY, AND NUCLEAR REACTOR SYSTEMS AND PROCESSES OPERATED THEREWITH  
A process of producing ceramic-ceramic composites, including but not limited to nuclear fuels, and composites capable of exhibiting increased thermal conductivities. The process includes milling a...
US20100044892 Separating Device For Sintering Shoes  
Device comprising means of separating at least two sintering shoes for transporting nuclear fuel pellets capable of moving according to a first axis (X) and of which two end faces are in contact...
US20100061501 CRITICALITY PREVENTION DEVICES AND METHODS IN NUCLEAR FUEL PRODUCTION  
The invention concerns a vessel for processing, transfer, accumulation and/or transfer of material containing civilian or military origin plutonium, in the form of plutonium oxide, carbide and/or...
US20130208848 SOLID INTERFACE JOINT WITH OPEN PORES FOR NUCLEAR CONTROL ROD  
A new interface between the cladding and the stack of pellets in a nuclear control rod. According to the invention, an interface joint made of a material transparent to neutrons, in the form of a...
US20080185743 METHOD OF MANUFACTURING SINTER-ACTIVE U3O8 POWDER AND METHOD OF PRODUCING NUCLEAR FUEL PELLETS UTILIZING THE SAME  
There is provided a method of producing U3O8 powder having large surface area and small particle size by oxidizing defective UO2 pellets and manufacturing nuclear fuel pellets which are stable in...
US20130010914 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...
US20090256271 Powder Dispenser, Notably for Pelletizer and Method for Making Nuclear Fuel Pellets  
The object of the present invention is mainly a powder dispenser including a casing capable of impulsing the powder in a reciprocal movement on a plane along a determined displacement direction...
US20140158943 MECHANICAL PROCESS FOR CREATING PARTICLES IN A FLUID  
A method of producing at least one of microscopic and submicroscopic particles includes providing a template that has a plurality of discrete surface portions, each discrete surface portion having...
US20090200691 Process for the Manufacture of a Dense Nuclear Fuel Material  
This invention relates to a process for manufacturing a dense material containing UO2, comprising: a) introducing at least two powders each comprising uranium dioxide UO2 into a vibrating grinder,...
US20070284766 Method for the Production of Nuclear Fuel Pellets  
A process for manufacturing nuclear fuel pellets through sintering of a material containing uranium dioxide obtained from a powder from a power originating from a process for a conversion of...
US20050106098 Microparticles and methods for their production  
Microparticles having a metal-containing core encapsulated in a graphitic shell containing hetero atoms are made by forming, in a liquid medium, colloidal particles containing a metal-oxo species...
US20090324953 HIGH BURN-UP NUCLEAR FUEL PELLETS  
A sintered nuclear fuel pellet, in particular for use in PWR or BWR nuclear reactors consists of grains having a size of less than 1 μm. A method of manufacturing such pellet is also disclosed.
US20130077731 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....
US20100014625 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...
US20140153687 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...
US20110274892 BIAXIALLY ORIENTED BIO-BASED POLYOLEFIN FILMS AND LAMINATES  
A laminate film including at least one bio-based polyolefin layer including at least 53 pMC of radiocarbon (14C) content is disclosed. The laminate film may include additional layers such as a...

Matches 1 - 50 out of 62 1 2 >