Abstract: The invention relates to installations for fiber optic monitoring of articles, and apparatus and methods for forming such installations, including a modular system and components for forming a fiber optic monitoring installation. Applications of the invention include the monitoring of vessels, chambers, and fluid conduits in industrial processing plants, and the invention has particular application to monitoring large vessels, for example temperature monitoring of vessels used in catalytic reforming processes. Convenient installation on or removal from the article being monitored is achieved by providing a support structure for the fiber optic length, which presents the fiber optic length in a preconfigured orientation suitable for monitoring the article. In a particular embodiment of the invention, the fiber optic length is disposed on a panel in a plurality of dense spiral patterns.

Abstract: A system may include first and second qubits that cross one another and a first coupler having a perimeter that encompasses at least a part of the portions of the first and second qubits, the first coupler being operable to ferromagnetically or anti-ferromagnetically couple the first and the second qubits together. A multi-layered computer chip may include a first plurality N of qubits laid out in a first metal layer, a second plurality M of qubits laid out at least partially in a second metal layer that cross each of the qubits of the first plurality of qubits, and a first plurality N times M of coupling devices that at least partially encompasses an area where a respective pair of the qubits from the first and the second plurality of qubits cross each other.

Abstract: 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 the matrix and the fibers, the matrix including silicon carbide as well as at least one of the following additional carbides: titanium carbide (TiC), zirconium carbide (Zrc), and ternary titanium silicon carbide (Ti3SiC2). When irradiated and at temperatures of between 800° C. and 1200° C., said cladding can mechanically maintain the nuclear fuel within the cladding while enabling optimal thermal-energy transfer towards the coolant. The invention also relates to a method for making the nuclear fuel cladding.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

Abstract: 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.

Abstract: The formation in quantity of various different populations of a substance being studied with multiple combinations of distribution form and distribution density by dripping a suspension of a single concentration of the substance onto a masking member of a certain specified structure placed on a substrate by making use of the sedimentation of said substance.

Abstract: This invention relates to a method of preparing nuclear fuel including the step of depositing at least two adjacent series of layers (16, 18) around a kernel (12) of fissile material, each series comprising a layer of pyrolytic carbon (16) contiguous with a layer of silicon carbide (18) and each layer (16, 18) having a thickness of at most (10) micrometres, such that alternate layers of (16, 18) of pyrolytic carbon and silicon carbide are deposited around the kernel (12). The invention extends to a nuclear fuel element (10).

Abstract: The invention relates to a jet spouted bed reactor, comprising a cylindrical area, a gas injection pipe at the base of the cylindrical area, and a transition area, connecting the upper end of the pipe to the base of the cylindrical area, this transition area having a convex profile in a plane extending through the axis (YY?) of flow of a fluid in the pipe.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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 (Ti3SiC2). When irradiated and at temperatures of between 800° C. and 1200° C., said cladding can mechanically maintain the nuclear fuel within the cladding while enabling optimal thermal-energy transfer towards the coolant. The invention also relates to a method for making the nuclear fuel cladding.

Abstract: A disinfectant surface provides a material layer and alpha-particle emitters embedded in the material layer and located in proximity to a surface of the material layer for emitting alpha particles through the surface for disinfecting any matter contacting the surface

Abstract: A method of forming a corrosion resistant neutron absorbing coating comprising the steps of spray or deposition or sputtering or welding processing to form a composite material made of a spray or deposition or sputtering or welding material, and a neutron absorbing material. Also a corrosion resistant neutron absorbing coating comprising a composite material made of a spray or deposition or sputtering or welding material, and a neutron absorbing material.

Abstract: A method for applying a burnable poison onto the cladding of a nuclear fuel rod (2) which comprises, providing a nuclear fuel rod (2) and at least one application device (8), rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod (2) by spraying an abrasive material onto the nuclear fuel rod via the application device (8) while adjusting the position of the application device in relation to the nuclear fuel rod (2), and applying burnable poison particles (33) onto the outer surface (6) of the nuclear fuel rod (2) by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device (8) 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 (6) of the cladding.

Abstract: Methods for manufacturing porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's). Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, a thin coating of nuclear fuel may be deposited inside of a highly porous skeletal structure made, for example, of reticulated vitreous carbon foam.

Abstract: 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 (12) of fissile material. The invention extends to a coated nuclear fuel particle (10).

Abstract: The method of protectively coating metallic uranium which comprises dipping the metallic uranium in a molten alloy comprising about 20-75% of copper and about 80-25% of tin, dipping the coated uranium promptly into molten tin, withdrawing it from the molten tin and removing excess molten metal, thereupon dipping it into a molten metal bath comprising aluminum until it is coated with this metal, then promptly withdrawing it from the bath.

Abstract: A metallic uranium article having a protective coating of a copper-tin alloy containing from 45 to 50% by weight of copper and from 55 to 50% by weight of tin, said alloy being firmly bonded to the metallic uranium.

Abstract: A method of making a circuitized substrate such as a printed circuit board having at least one hole therein which comprises the steps of providing a layer of dielectric, forming at least one (and preferably several) holes therein, providing a fill member including a quantity of fill material and reinforcement means located within the fill material, positioning the fill member on the dielectric over the holes and thereafter applying a predetermined force sufficient to cause only the fill material to be forcibly driven into the accommodating hole(s), not the reinforcement means. Subsequent steps can include forming a layer of circuitry on the substrate's external surface and over the filled holes such that an electrical component such as a ball grid array (BGA), semiconductor chip, etc. may be directly positioned on and/or over the hole(s). A fill member usable with the method is also provided.

Abstract: A method of jacketing a uranium slug to an aluminum container comprising applying a coating to the exterior of the container, the coating consisting of colloidal graphite in water, permitting the coating to dry, applying an alloy of aluminum and silicon to the interior surface of the container at a temperature between 588° C. and 594° C., inserting the slug into the container in complete contact with the alloy, and quenching the assembly.

Abstract: A method of jacketing a body of fissionable material within a nonfissionable jacket having a cup-shaped body open at one end and a cap effecting closure at said end comprising the steps of inserting the cup-shaped body into a tightly fitting cup-shaped sleeve; completely submerging said assembly in a bonding bath of a molten metallic bonding material, allowing the inner body to fill with molten bonding material; dipping the fissionable body into the open end of said assembly while under the surface of the bonding bath; closing the open end of the assembly with the cap while under the surface of the bonding bath; removing the complete assembly from the bonding bath; quenching in cold water; and removing the sleeve.

Abstract: The present invention relates to a coating method for the preparation of a coated nuclear fuel. Particularly, the present invention relates to the coating method of nuclear fuel surface with more than two coated layers of carbides, borides or nitrides and their compounds comprising deposition or permeation steps of i) elements or mixture that can form carbides, borides or nitrides and ii) a layer of pyrolytic carbon or boron prepared by chemical vapor deposition(CVD) or sputtering in sequence or in reverse sequence, or nitrogen prepared by gas permeation in sequence, on the nuclear fuel surface. The coated layers are formed with carbides, borides, nitrides or their mixture at high temperature and pressure by a combustion synthesis.

Abstract: A pyrolytic carbon coated nuclear fuel particle and method of making it. The fuel particle has a core composed of a refractory compound of an actinide metal. The pyrolytic carbon coating surrounds the core so as to provide a void volume therebetween. The coating has an initial density of no greater than 1.45 grams/cm.sup.3 and an anisotropy factor than 3.0 and a final density upon heat treatment above about 2000.degree. C. of greater than 1.7 grams/cm.sup.3 and an anisotropy factor greater than 5.

Abstract: A process for manufacturing an organic electroluminescent device, including the steps of sequentially forming a hole transport layer, a bipolar transport layer at need, and an electron transport layer on a transparent electrode side of a transparent substrate having a transparent electrode. After a recombination region layer for electrons and holes of the transport layers is formed, three kinds of fluorescent pigment R, G and B are applied to an upper surface of the recombination region layer. Subsequently, the kinds of fluorescent pigment are heated to be diffused in the recombination layer so that the kinds of fluorescent pigment and the recombination layer constitute a luminescent layer. An organic electroluminescent device produced by this process is disclosed.

Abstract: A protective coating to reduce stress corrosion cracking of zirconium alloy sheathing in nuclear reactors. The coating is graphite based and includes ZrO.sub.2 and ethyl cellulose and acts as a sacrificial layer to immobilize fission products by formation of Zr.sub.x I.sub.y C type compounds which do not cause stress corrosion cracking.

Abstract: A method for containing or removing contamination from a substrate includes applying a material such as a polyurea elastomer to the contaminated substrate. Preferably, the material sets in less than about 1 hour and is substantially unaffected by exposure to radiation. The contaminants can be contained or shielded on the substrate by the material to reduce exposure to the contaminants. In one preferred embodiment, this invention relates to the encapsulation of objects or surfaces to shield persons in the area from contamination. Alternatively, the material can be removed from the substrate to remove contaminants. Preferably, the material provides a Decontamination Factor of at least about 10. In another preferred embodiment, the material is applied hot to the contaminated substrate to increase its effectiveness in removing contaminants. The present method can also prevent contamination of an uncontaminated substrate.

Abstract: This invention relates to a process for the preparation of lithium aluminosilicate or gamma lithium aluminate ceramics having a controlled microstructure and stoichiometry.According to this process, mixing takes place accompanied by stirring in a short chain anhydrous alcohol of an unpolymerized liquid aluminium alkoxide and optionally a silicon alkoxide with a hydrated or unhydrated lithium hydroxide, followed by the addition of water in order to hydrolyze the mixture and obtain, after drying, beta LiAlO.sub.2 powder.This powder can be directly compacted and then sintered at temperatures of 800.degree. to 1150.degree. C. without prior calcination giving a gamma lithium aluminate ceramic with a controlled stoichiometry and microstructure (grains of 0.1 to 10 .mu.m).

Abstract: A fluidized bed reactor arrangement and method for forming a metal carbide coating on a substrate containing graphite in which a bed of particles inclusive of the substrate is fluidized using a fluidizing gas containing a metal halide vapor formed by reacting a metal halide gas with a carbide forming metal selected from Group IVb through VIIb of the periodic table and maintaining the temperature of the fluidized bed above 1500.degree. C.

Abstract: A method of containing hazardous and toxic wastes includes the steps of irporating the dried waste, in a salt form, in melted polymer, such as asphalt, and forming the waste salt and asphalt blend into aggregate pellets. The pellets are coated with a powdered coating material that is compatible with a portland cement-based mortar or other cementitious material which is used. The coated particles are mixed with mortar to form a polymer-aggregate concrete and cast into wasteforms for storage or burial. If it is desirable to produce a waste form with a continuous layer of mortar on the exterior of the concrete monolith the mold can be placed on a turntable and spun, or otherwise exposed to a centrifugal force to force the mortar to the outside of the mold. Centrifugal separation is possible because the polymer-waste mixture typically has a specific gravity near 1.5 while that of the cementitious mixture is typically greater than 2.0.

Abstract: A method and composition for stabilizing and isolating hazardous, radioactive or mixed waste materials of particulate and solid types, which comprises providing a non-toxic one component aqueous mixture of an acrylic polymer containing a thixotropic agent, a vinyl acetate-ethylene copolymer containing a thixotropic agent, or a vinyl chloride copolymer latex containing a thixotropic agent, and applying the mixture over surfaces of hazardous material in an amount sufficient to form a flexible impermeable coating or foam. The mixture may be applied by spraying to form a coating having a thickness of about 0.5 to about 5.0 centimeters when dry. The coated waste material may then be disposed of in conventional manner.

Abstract: A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing on a weight percentage basis tin in a range of 0.4 to 1.0 percent and typically 0.5; iron in a range of 0.3 to 0.6 percent, and typically 0.46 percent; chromium in a range of 0.2 to 0.4 percent, and typically 0.23 percent; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 1200 to 2500 ppm, typically 1800 to 2200 ppm. The high oxygen level assists in reducing hydrogen uptake of the alloy compared to Zircaloy-4, for example.

Abstract: A method for coating a nuclear fuel pellet is provided in which a liquid sol is formed containing the makings of a rare earth metal oxide. The liquid sol is applied to the exterior surface of the nuclear fuel pellet and the pellet is baked to form a solid coated pellet. If desired, zirconium diboride may be dispersed within the rare earth metal oxide matrix. Preferably, the rare earth metal oxide is either erbium oxide or gadolinia.

Abstract: A method of encapsulating a toxic material with a resinous plastic wherein the toxic material is admixed and coated with the resinous plastic to result in an encapsulated product having a protective skin thereover. The method involves an extrusion step followed by a severing of the extruded product into discrete particles for either subsequent injection or compression molding or additional extruding with additional resinous plastic. Geometric forms result which can indicate the type of toxic material as well as be of a size so as not to be ingested by animals and have imprinted warning indicia. Liquid as well as solid toxic materials can be encapsulated.

Abstract: A method of passivating the surface of particulate uranium oxides is disclosed comprising a process of continuously contacting uranium oxide particles with an oxygen containing and cooling counter flowing gas stream. The treatment produces a protective surface which inhibits subsequent oxygen chemisorption of the particulate uranium oxides.

Abstract: A method of compacting radioactive metal wastes comprising enclosing the radioactive metal waste in vacuo in a capsule, placing the capsule into a pressure container, and subjecting the capsule to an increased pressure at a high temperature to compact the waste. The compacting treatment is conducted in a state in which the atmosphere within the pressure container contains water molecules in an amount, in terms of the total weight W (g) thereof, the amount being preferably in the range of:1.3.times.10.sup.-6 .times.V.ltoreq.Wwherein V (cm.sup.3) is the volume of the compacting space in the pressure container. Alternatively, an oxide coating is formed on the outer surface of the capsule before the capsule is placed into the pressure container, or the formation of the oxide coating is followed by the compacting treatment conducted in the above-mentioned state.

Abstract: Methods for making nuclear fuel compacts containing precise amounts of nuclear fuel material which exhibit low heavy metal contamination and fewer defective coatings following compact fabrication using a hardenable binder including petroleum pitch or the like. Nuclear fuel particles having a multiple layer fission-product-retentive barrier, with a dense outer layer thereof being surrounded by a protective overcoating, e.g., pyrocarbon having a density between about 1 and 1.2 g/cm.sup.3, that is encapsulated within a thin shell of pyrocarbon from about 1.7 to about 2 g/cm.sup.3 in density, can be precisely metered to create charges containing very precise amounts of nuclear fuel material that can be pre-compacted in molds under relatively high pressures and then combined with the fluid binder which is ultimately carbonized to produce carbonaceous compacts containing very precise nuclear fuel loadings.

Abstract: In order to prevent the formation of a hydrogen atmosphere in a free gas ce usually available in the storage containers of radioactive waste, potassium permanganate is dispersed in a suitable carrier within the storage barrel provided for the waste. When the radioactive waste is first encased in cement before being put in a storage barrel, the potassium permanganate is introduced into the cement before it sets by mixing in a solution or crystals. Alternatively the compressed or solidified waste is enveloped in a porous non-reducing aggregate of carrier materials, such as particles of aluminum oxide, on the exposed surfaces of which potassium permanganate is applied or which is mixed with potassium per manganate particles. The waste and the enveloping permanganate-containing carrier material are then securely enclosed in a common container.

Abstract: The invention concerns a method for conditioning in a thermosetting resin a quantity of waste stored in water.According to the invention, a liquid hardening agent, immiscible with water and having a density greater than that of the water, is used in order to harden the resin; this hardening agent is then mixed with the waste stored in the water and then the waste is left to decant in the hardening agent; then the water present above the decanted waste transferred into the liquid hardening agent is extracted and the waste transferred into the liquid hardening agent is mixed with the epoxy resin so as to obtain a solid block.In particular, the waste may be ion exchanger resins. Adding of the hardening agent to the waste stored in the water makes it possible to limit a temperature rise during hardining and to obtain solid products having an improved density.

Abstract: Metallic or ceramic hollow spheres are produced by applying a solid layer to a substantially spherical particle of foamed polymer and the coated polymer cores are pyrolyzed with formation of vapor. In order to permit an economical production of the hollow spheres and a wide selection from a wide range of metallic or ceramic materials, the particles consisting of foamed polymer are treated in a state of agitation with an aqueous suspension which contains dissolved or suspended binder and metallic and/or ceramic powder particles, whereby a coating is formed on said polymer particles. The coating is dried, the polymer particles and least part of the binder are subsequently pyrolyzed at temperatures from 400.degree. to 500.degree. C. with formation of vapor while they are agitated and the resulting metallic and/or ceramic hollow spheres are sintered at temperatures from 1000.degree. to 1500.degree. C. while they are agitated.

Abstract: A process for overcoating granules with overcoating material in a granulator by providing the inside surface of the granulator, before introduction of the granules, with a layer of the overcoating material in a thickness of 0.1 to 1 mm, maintaining a preset entrainment height of the granules during the granulation process, and adding the overcoating material in the flowing particle bed. The deposited layers are very uniform.

Abstract: The invention relates to a process for the conditioning of radioactive or toxic waste in epoxy resins and a polymerizable mixture with two liquid constituents usable in this process.This process consists of incorporating the waste into a polymerizable mixture incorporating at least one epoxy resin, pitch and at least one epoxy resin hardener and allowing the thus obtained mixture to harden.Generally the mixture comprises at least 50% by pitch weight and can be used for treating radioactive waste constituted by large objects and organic liquids.

Abstract: Disclosed is a method of reoxidizing a partially oxidizable metal or metal oxide powder. The powder is spread on a first sloped trough to form a layer of less than about a half inch in thickness. The layer of powder slides down the trough and falls onto a second trough sloped in the opposite direction, thereby inverting the powder on the second trough. While the powder is on the troughs, it is exposed to an amount of oxygen sufficient to partially oxidize the powder but insufficient to completely oxidize the powder.Also disclosed is apparatus useful for partially reoxidizing a partially oxidizable powder.

Abstract: A method is disclosed for coating a substrate with a uniformly smooth layer of a boron hydride polymer. The method comprises providing a reaction chamber which contains the substrate and the boron hydride plasma. A boron hydride feed stock is introduced into the chamber simultaneously with the generation of a plasma discharge within the chamber. A boron hydride plasma of ions, electrons and free radicals which is generated by the plasma discharge interacts to form a uniformly smooth boron hydride polymer which is deposited on the substrate.

Abstract: A process for forming a boron-containing coating on the internal surface of a zirconium or zirconium alloy hollow tube by heating the internal surface to a temperature of between 200.degree.-450.degree. C. and passing through the tube a mixture of a volatilized boron compound in helium or argon, such that the boron compound decomposes to form an integral boron containing coating on the internal surface.