Abstract: Disclosed embodiments include fuel ducts, fuel assemblies, methods of making fuel ducts, methods of making a fuel assembly, and methods of using a fuel assembly. An inner hollow structure has a first geometry and an outer hollow structure has a second geometry different from the first geometry. The first hollow structure is configured to expand in at least one dimension under stress and cause the first hollow structure to contact the second hollow structure. The second hollow structure distributes at least a portion of the stress of the first hollow structure.

Abstract: A method of controlling macroscopic strain of a porous structure includes contacting a porous structure with a modifying agent which chemically adsorbs to a surface of the porous structure and modifies an existing surface stress of the porous structure. A device in one embodiment includes a porous metal structure, which when contacted with a modifying agent which chemically adsorbs to a surface of the porous metal structure, exhibits a volumetric change due to modification of an existing surface stress of the porous metal structure; and a mechanism for detecting the volumetric change. Additional methods and systems are also presented.

Abstract: Radiological containment bags for use in storing alpha particle emitting waste are described. The radiological containment bags are formed of a multilayer film with an inner layer of the film being a sacrificial layer that lies between the interior of the bag and a structural polymeric layer. The sacrificial layer includes a flexible composite material that in turn includes a polymeric matrix and an alpha particle energy absorber incorporated in the polymeric matrix. The sacrificial layer can include a chromophore that can detect early degradation of the sacrificial material.

Abstract: A method for making a gradient index infrared transmitting optic by thermally treating a preform, where the preform comprises two or more infrared transmitting glasses having different compositions and optical properties, where there is an interface between adjacent glasses, where during the thermal treatment one or more chemical elements from the glasses diffuses through one or more interface resulting in a diffused gradient index optical element comprising a gradient in the chemical element concentration, and where the optical element has a gradient in refractive index and dispersion. Also disclosed is the related infrared transmitting optical element made by this method.

Abstract: The synthetic amorphous silica powder of the present invention is characterized in that it comprises a synthetic amorphous silica powder obtained by applying a spheroidizing treatment to a silica powder, and by subsequently cleaning and drying it so that the synthetic amorphous silica powder has an average particle diameter D50 of 10 to 2,000 ?m; wherein the synthetic amorphous silica powder has: a quotient of 1.00 to 1.35 obtained by dividing a BET specific surface area of the powder by a theoretical specific surface area calculated from the average particle diameter D50; a real density of 2.10 to 2.20 g/cm3; an intra-particulate porosity of 0 to 0.05; a circularity of 0.75 to 1.00; and an unmolten ratio of 0.00 to 0.25.

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: A polishing slurry can include zirconia particles. The polishing slurry can be used to polish conductive and insulating materials, and is particularly well suited for polishing oxide materials as well as metals. The characteristics of the zirconia particles can affect the polishing of workpieces. By selecting the proper characteristics, the polishing slurry can have a good material removal rate while still providing an acceptable surface finish. The zirconia particles can be used as a replacement for, or in conjunction with, ceria or other abrasive particles. The content of zirconia particles in the polishing slurry may be less than a comparable polishing slurry having silica or alumina particles.

Abstract: The present disclosure relates to porous ceramic articles and a method of making the same. The porous ceramic articles have microstructure of sinter bonded or reaction bonded large pre-reacted particles and pore network structure exhibiting large pore necks. The method of making the porous ceramic articles involves using pre-reacted particles having one or more phases. A plastic ceramic precursor composition is also disclosed. The composition includes a mixture of at least one of dense, porous, or hollow spheroidal pre-reacted particles and a liquid vehicle.

Abstract: A composition based on cerium, zirconium and tungsten is described. The composition has a content expressed as an oxide, of which cerium is from 5% to 30% of the composition, tungsten is from 2% to 17% of the composition, and the remainder of the composition is zirconium. After aging at 750° C. under an air atmosphere including 10% water, it has a two-phase crystallographic structure having a tetragonal zirconia phase and a monoclinic zirconia phase, with no presence of a crystalline phase including tungsten. The composition can be used as a catalyst, especially in an SCR process.

Abstract: The present disclosure is directed to systems and methods that absorb waste into a metal-organic framework (MOF), and applying pressure to the MOF material's framework to crystallize or make amorphous the MOF material thereby changing the MOF's pore structure and sorption characteristics without collapsing the MOF framework.

Abstract: A method for treating a cladding within which there is a sintered material composed wholly or partly of sintered calcium hydride, the method comprising a step during which the sintered material is contacted with a reaction mixture comprising steam, carbon dioxide, and a chemically inert gas, the contacting being carried out for a duration allowing the sintered calcium hydride to be converted into a calcium carbonate powder. The treatment method provided by the invention results in a chemically inert waste, a limitation on the volume of wastes obtained, while allowing the removal or even recovery of these wastes by appropriate processing streams.

Abstract: Compositions comprising nanosized objects (i.e., nanoparticles) in which at least one observable marker, such as a radioisotope or fluorophore, is incorporated within the nanosized object. The nanosized objects include, for example, metal or semi-metal oxide (e.g., silica), quantum dot, noble metal, magnetic metal oxide, organic polymer, metal salt, and core-shell nanoparticles, wherein the label is incorporated within the nanoparticle or selectively in a metal oxide shell of a core-shell nanoparticle. Methods of preparing the volume-labeled nanoparticles are also described.

Abstract: A method of preparing radioisotope hybrid nanocomposite particles using a sol-gel reaction, and radioisotope hybrid nanocomposite particles prepared using the same are provided. The method includes preparing a complex precursor using a metal ion and an unshared electron pair reactive compound, growing hybrid nanocomposite particles based on the complex precursor by means of a sol-gel reaction, calcining the nanocomposite particles in the air to remove organic matters present in the nanocomposite particles, and irradiating the nanocomposite particles with neutrons to prepare radioisotope hybrid nanocomposite particles. The radioisotope nanocomposite particles prepared using the method can be used as diagnostic and therapeutic particles in the fields of oil refining, chemistry, cement, agriculture, water resources, environment, ocean, and medicine, and can also be used as a radioisotope tracer for evaluating the risk of nanomaterials.

Abstract: Using crystalline silica, mixed with cement powder, to reduce the heating of the cement paste caused by the hydration of said powder, during a process of packaging of radioactive waste, a formulation for the packaging of radioactive waste by cementing, which comprises such silica, a method for packaging radioactive waste implementing this formulation, and a package for packaging of radioactive waste which is obtained by this method.

Abstract: Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Abstract: A method for manufacturing a plurality of glass microspheres comprises: melting a batch into a first glass melt in a melter system, processing the first glass melt into a second glass, pulverizing the second glass into a plurality of glass fragments, thermally processing the plurality of glass fragments into a plurality of glass microspheres, providing at least one of a plurality of redox reactions and a plurality of events in at least one of the first glass melt and a melt of the second glass, and the plurality of redox reactions and the plurality of events are induced by a plurality of redox active group (RAG) components.

Abstract: A composition of matter that experiences an increase rate of radioactive emission is presented. The composition comprises a radioactive material and particles having affinity for Hydrogen or its isotopes. When exposed to Hydrogen, the composition's emission rate increases. Methods of production are also presented.

Abstract: A composition of matter that experiences an increase rate of radioactive emission is presented. The composition comprises a radioactive material and particles having affinity for Hydrogen or its isotopes. When exposed to Hydrogen, the composition's emission rate increases. Methods of production are also presented.

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) micrometers, 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 present invention is related to a method to obtain reactive [18F] fluorides in an organic medium suitable for radiolabelling without any azeotropic evaporation step, by the use of a solid phase extraction column containing a modified non-ionic solid support.

Abstract: A magazine for chain components of a chain with radiation sources comprises a housing as well as a first means for receiving chain components that is mounted in a pivotal manner in the housing and has recesses for receiving the chain components, a tension spring for driving the means for receiving the chain components, a sprocket being coupled in a pivotal manner to the means for receiving the chain components and being mounted in a pivotal position in the housing, and an ejector for ejection of the radiation sources. Furthermore, the magazine comprises an ejection lever which is mounted in a pivotal manner in the housing, whereby, in a first position, the ejection lever engages the sprocket, and in a second position it blocks the ejector.

Abstract: A matrix material for safe temporary and/or ultimate disposal of radioactive wastes suitable for the embedment of radioactive wastes, contains graphite and at least inorganic binder which can be glass, aluminosilicate, silicate, borate and lead sulfide.

Abstract: Formulations useful for preparing hydrous hafnium oxide gels contain a metal salt including hafnium, an acid, an organic base, and a complexing agent. Methods for preparing gels containing hydrous hafnium oxide include heating a formulation to a temperature sufficient to induce gel formation, where the formulation contains a metal salt including hafnium, an acid, an organic base, and a complexing agent.

Abstract: The present invention discloses alpha particle emitting, radioactive constructs capable of killing large tumors (>1 mm in diameter), or other cells involved in human or animal diseases such as virus infected cells, autoimmune cells, or other pathological cells, including normal cells, that are targets for destruction, to achieve a therapeutic result. The alpha-emitting constructs have high specific activity.

Abstract: A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.

Abstract: Neutron scintillating materials are provided, including boron substitution scintillation materials, boron and Li substitution scintillation materials, and Gd-based substitution scintillation materials.

Abstract: Formulations useful for preparing hydrous cerium oxide gels contain a metal salt including cerium, an organic base, and a complexing agent. Methods for preparing gels containing hydrous cerium oxide include heating a formulation to a temperature sufficient to induce gel formation, where the formulation contains a metal salt including cerium, an organic base, and a complexing agent.

Abstract: A forensic marker is disclosed including a marker that is added to the host material and is detectable for at least the expected life of the host material. The marker is inert with respect to the host material in that it does not significantly affect the desired qualities of the host material (e.g. weight, adhesive properties, structural integrity, etc). The marker is detectable, for example, by instruments, during the life of the host material.

Abstract: Heteronuclear radioisotope nanoparticle of core-shell structure and a preparation method thereof are provided. The Heteronuclear radioisotope nanoparticle of core-shell structure comprising core of two different radioisotopes selected from a group consisting of 198Au, 63Ni, 110mAg, 64Cu, 60Co, 192Ir and 103Pd, and a shell comprising Si02 surrounding the core. The Heteronuclear radioisotope nanoparticle of core-shell can be used as a tracer for the purpose of detecting variation of volume ratio or for the evaluation of the behavior characteristic of a water resource, based on information about phase ratio in the flow of multiphase fluid existing in a process which is operated under extreme condition such as high temperature and/or high pressure conditions.

Abstract: A waste form for and a method of rendering hazardous materials less dangerous is disclosed that includes fixing the hazardous material in nanopores of a nanoporous material, reacting the trapped hazardous material to render it less volatile/soluble, and vitrifying the nanoporous material containing the less volatile/soluble hazardous material.

Abstract: Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Abstract: Manufacturing a gamma radiation source includes providing an unacceptable material that is a combination of acceptable and unacceptable isotopes, transforming the unacceptable material into an acceptable material by removing unacceptable isotopes from the unacceptable material, leaving only acceptable isotopes, mixing selenium-74 and the acceptable material and heating the mixture to cause the constituents to inter-react and subsequently subjecting the reaction product to irradiation to convert at least a proportion of the selenium-74 to selenium-75. Manufacturing a gamma radiation source may also include adding at least one other acceptable material to the mixture. The at least one other acceptable material may be added to the mixture prior to heating the mixture. The unacceptable material may be selected from the group consisting of: Zinc, Titanium, Nickel, Zirconium, Ruthenium, Iron, Silver, Indium, Thallium, Samarium, Ytterbium, Germanium, and Iridium.

Abstract: A composition of matter that experiences an increase rate of radioactive emission is presented. The composition comprises a radioactive material and particles having affinity for Hydrogen or its isotopes. When exposed to Hydrogen, the composition's emission rate increases. Methods of production are also presented.

Abstract: Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI2, CuI, or Bi5O7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425° C. to 550° C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500° C. (below the silver iodide sublimation temperature of 500° C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.

Abstract: Neutron source comprising a composite, said composite comprising crystals comprising BeO and AmBe13, and an excess of beryllium, wherein the crystals have an average size of less than 2 microns; the size distribution of the crystals is less than 2 microns; and the beryllium is present in a 7-fold to a 75-fold excess by weight of the amount of AmBe13; and methods of making thereof.

Abstract: Compositions comprising nanosized objects (i.e., nanoparticles) in which at least one observable marker, such as a radioisotope or fluorophore, is incorporated within the nanosized object. The nanosized objects include, for example, metal or semi-metal oxide (e.g., silica), quantum dot, noble metal, magnetic metal oxide, organic polymer, metal salt, and core-shell nanoparticles, wherein the label is incorporated within the nanoparticle or selectively in a metal oxide shell of a core-shell nanoparticle. Methods of preparing the volume-labeled nanoparticles are also described.

Abstract: Disclosed herein are a method and an apparatus to identify alpha-emitting radionuclides and to measure absolute alpha radioactivity using a low temperature detector. A 4? metallic absorber which encloses a radioactive material containing alpha-emitting radionuclides absorbs the total alpha decay energy in the form of thermal energy. The corresponding temperature changes are measured by a low temperature detector attached to the 4? absorber with high energy resolution. The identification of alpha-emitting radionuclides is declared by comparing the measured temperature signal with characteristic decay energy of radionuclides. The absolute amount of the radionuclides is determined by counting the number of the pulses for each of the identified nuclides.

Abstract: Neutron source comprising a composite, said composite comprising crystals comprising BeO and AmBe13, and an excess of beryllium, wherein the crystals have an average size of less than 2 microns; the size distribution of the crystals is less than 2 microns; and the beryllium is present in a 7-fold to a 75-fold excess by weight of the amount of AmBe13; and methods of making thereof.

Abstract: This invention provides a dripping nozzle device to produce ADU particles with good sphericity, a device for recovering a feedstock liquid to prepare a uniform feedstock liquid, a device for supplying a feedstock liquid to form drops with a uniform volume, a device for solidifying the surfaces of drops so that the drops will not deform easily when they fall onto and hit the surface of an aqueous ammonia solution, a device for circulating an aqueous ammonia solution so that the uranyl nitrate in the drops can be changed to ammonium diuranate completely, to such an extent that uranyl nitrate in the center of each drop is changed to ammonium diuranate, and an apparatus for producing ammonium diuranate particles with good sphericity. The dripping nozzle device is provided with a single vibrator to vibrate nozzles simultaneously. The device for recovering a feedstock liquid recovers the feedstock liquid remaining in the nozzles and mixes it with a fresh feedstock liquid.

Abstract: The present invention is related to a method to obtain reactive [18F] fluorides in an organic medium suitable for radiolabelling without any azeotropic evaporation step, by the use of a solid phase extraction column containing a modified non-ionic solid support.

Abstract: The present invention is directed to a generator apparatus for separating a daughter gallium-68 radioisotope substantially free of impurities from a parent gernanium-68 radioisotope, including a first resin-containing column containing parent gernanium-68 radioisotope and daughter gallium-68 radioisotope, a source of first eluent connected to said first resin-containing column for separating daughter gallium-68 radioisotope from the first resin-containing column, said first eluent including citrate whereby the separated gallium is in the form of gallium citrate, a mixing space connected to said first resin-containing column for admixing a source of hydrochloric acid with said separated gallium citrate whereby gallium citrate is converted to gallium tetrachloride, a second resin-containing column for retention of gallium-68 tetrachloride, and, a source of second eluent connected to said second resin-containing column for eluting the daughter gallium-68 radioisotope from said second resin-containing column.

Abstract: A self-contained source of gamma-ray and neutron radiation suitable for use as a radiation surrogate for weapons-grade plutonium is described. The source generates a radiation spectrum similar to that of weapons-grade plutonium at 5% energy resolution between 59 and 2614 keV, but contains no special nuclear material and emits little ?-particle radiation. The weapons-grade plutonium radiation surrogate also emits neutrons having fluxes commensurate with the gamma-radiation intensities employed.

Abstract: 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 a surface geometry selected to impart a desired geometrical property to a particle while being produced; depositing a constituent material of the at least one of microscopic and submicroscopic particles being produced onto the plurality of discrete surface portions of the template to form at least portions of the particles; separating the at least one of microscopic and submicroscopic particles comprising the constituent material from the template into a fluid material, the particles being separate from each other at respective discrete surface portions of the template; and processing the template for subsequent use in producing additional at least one of microscopic and submicroscopic particles.

Abstract: The present invention relates generally to synthesis of radioactive material, such as a tritiated polymer, and an apparatus for generating electrical current from the nuclear decay process of a radioactive material. In one embodiment, the invention relates to an energy cell (e.g., a battery) for generating electrical current derived from particle emissions occurring within a radioactive material such as a tritiated polymer) on pore walls of a porous semiconductor. The radioactive material may be introduced into the energy cell by a wetting process.

Abstract: The invention relates to an apparatus for preparing a small amount of a radioactive substance combination, including a one-part body, a mixing device integrated in the body and adapted to receive a small amount of chemical substances, and at least one receptacle integrated in the body and connected to the mixing device and adapted to hold a small amount of a chemical substance.

Abstract: Solid-state scintillating compositions for detecting neutrons comprise a Li4Zn(PO4)2 host lattice. Methods of making scintillating compositions comprise: dissolving a lithium-6 precursor and a zinc precursor in a solvent to form a solution; combining phosphoric acid with the solution; combining a base with the solution to form a precipitate; and heating the precipitate to form a Li4Zn(PO4)2 host lattice.

Abstract: New chelating agents as well as their tricarbonyl complexes with technetium and rhenium and the use of these compounds in radiodiagnosis and radiotherapy are described. As a peculiarity of this invention, synthesis and coupling of the chelating systems to (bio)molecules is performed simultaneously. The new chelating agents are coupled to substances that accumulate in the diseased/targeted tissue.

Abstract: Composite scintillator material consisting of a binderless sintered mixture of a Lithium (Li) compound containing 6Li as the neutron converter and Y2SiO5:Ce as the scintillation phosphor, and the use of this material as a method for neutron detection. Other embodiments of the invention include various other Li compounds.

Abstract: A cathode including an active material composite and a lithium battery using the same. The active material composite of the cathode includes a mixed oxide complex and a lithium-containing compound, the lithium-containing compound having a metal based compound coated on the surface of the lithium-containing compound.

Abstract: The subject matter of the present invention is marked inorganic additives, a method for their production and also their use.