Abstract: A method for preparing a powder comprising an intimate mixture of U3O8 particles and PuO2 particles and which may further comprise particles of ThO2 or NpO2. The method comprises: preparing, via oxalic precipitations, an aqueous suspension S1 of particles of uranium(IV) oxalate and an aqueous suspension S2 of particles of plutonium(IV) oxalate; mixing the aqueous suspension S1 with the aqueous suspension S2 to obtain an aqueous suspension S1+2; separating the aqueous suspension S1+2 into an aqueous phase and a solid phase comprising the particles of uranium(IV) oxalate and the particles of plutonium(IV) oxalate; and calcining the solid phase to convert (1) the particles of uranium(IV) oxalate to particles of triuranium octoxide and (2) the particles of plutonium(IV) oxalate to particles of plutonium(IV) dioxide, whereby the powder is obtained.

Abstract: The invention is related to nuclear technologies, in particular, to the technology of producing nuclear oxide fuel for fuel elements, this oxide fuel can be used for manufacturing palletized nuclear fuel from uranium dioxide to be consumed by NPPs. The essence of the invention: this method of producing palletized nuclear fuel from uranium dioxide involves preparation of uranium dioxide moulding powder with/without uranium oxide, at this point powdered uranium dioxide is used as a raw material for preparation of moulding powder. Powdered uranium dioxide should be in the following proportion: O/U=2.37±0.04, it is obtained using a renowned method—by air heating of powdered uranium dioxide (ceramic grade) with the following proportion O/U=2.01?2.15. The technical result of the invention is increased mechanical strength of sintered pellets and a larger grain size of sintered pellets.

Abstract: A multiphase composite, formed by freeze-casting, lyophilization, and sintering, has sintered particles forming a scaffold having at least one region of aligned porosity; and a second phase formed in pores of the scaffold. In a particular embodiment, the second phase is a nuclear fuel, in another, the first phase is a nuclear fuel, and in others, both phases are nuclear fuels. In some embodiments, the first phase is a ceramic, and in other embodiments a metal such as stainless steel. In other embodiments, the second phase is a metal, and in other embodiments a ceramic. In some embodiments the second phase is positioned in a subset of pores of the scaffold, at least some additional pores being filled with a third phase. In embodiments, the second phase is also sintered.

Abstract: Methods of preparing particles using a sonication device are disclosed. The methods include directing a particle forming solution containing a particle forming liquid and a particle forming agent as a stream into contact with a sonicating tip of a sonication device under conditions sufficient to transform the stream containing the particle forming solution into a plurality of droplets having a substantially uniform size. The plurality of droplets are contacted with a hardening solution under conditions sufficient to solidify the droplets into particles having a substantially uniform particle size which are then recovered. Particles made in accordance with the methods can be solid or semi-solid and range in size from sub-micron to over 100 microns in diameter.

Abstract: Apparatuses and methods of forming hollow spheres are provided. Hollow sphere forming apparatus incorporate a bubble forming nozzle assembly in which outlets for gas and liquid materials are disposed substantially coaxially. The relative positions of the gas and liquid outlets are adjustable in at least one dimension (e.g., axially, radially or angularly relative to each other), such that a more uniform annular exit region for the gas and liquid outlets may be configured, such that more symmetric bubbles may be formed thus reducing the rejection rate in solidified bubbles due to asymmetry or decentering of entrapped gas.

Abstract: This dissolvent is an inorganic compound of silica gel that is stabile and lasts for decades. Pleasant gold color, no evident odor or vapor, and it will not spill, or degrade over the decades, while awaiting use. After full and complete use with several syringes needles being dissolved at one location, these sharps will blacken and corrode and dissolve away, and the gel then becomes ordinary harmless waste to be conveniently discarded. This dissolvent gel will blunt sharp points and edges of sharps instantly to become totally useless. The useless sharps and needles will carry no infection, no living organism, no viruses, no pathogens, no bacterium, just nothing, just scrap! Nothing sharp or dangerous or infectious is left to be in the trash, or in the landfill, or in the ocean—it's just harmless scrap.

Abstract: An interconnect element includes a semiconductor or insulating material layer that has a first thickness and defines a first surface; a thermally conductive layer; a plurality of conductive elements; and a dielectric coating. The thermally conductive layer includes a second thickness of at least 10 microns and defines a second surface of the interconnect element. The plurality of conductive elements extend from the first surface of the interconnect element to the second surface of the interconnect element. The dielectric coating is between at least a portion of each conductive element and the thermally conductive layer.

Abstract: A method of producing a localized concentration of energy comprises creating at least one shockwave (10) propagating through a non-gaseous medium (8) so as to be incident upon a pocket of gas (2) within the medium (8). The pocket of gas (2) is attached to a surface (6) comprising a depression (4) shaped so as partially to receive the gas pocket (2). An apparatus for producing a localized concentration of energy comprises a non-gaseous medium (8) having therein a pocket of gas (2). The pocket of gas (2) is attached to a surface (6) comprising a depression (4) shaped so as partially to receive the gas pocket (2). The apparatus further comprises means for creating at least one shockwave (10) propagating through the medium (8) so as to be incident upon the pocket of gas (2).

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: 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: Process for treating spent nuclear fuel (SNF) to make mixed metal oxides of UO3 and PuO2 to prevent nuclear proliferation. The process comprises the steps of (1) dissolving spent nuclear fuel in an acidic solution in the presence of an agent that reduces Pu+6 to Pu+4 and an agent that oxidizes Pu+3 to Pu+4; (2) extracting U+6 and Pu+4 from acidic solution with an organic solvent comprising a ligand that binds U+6 and Pu+4 and which is soluble in the organic solvent; (3) jointly extracting U+6 and Pu+4 from the organic solvent with an acidic aqueous solution; and (4) precipitating a mixture of U+6 and Pu+4 by adding a carboxylic acid to the acidic aqueous solution. The U+6 and Pu+4 precipitate is then be calcined to form a mixed metal oxide of UO3 and PuO2. Additional steps can result in the formation of a mixed metal oxide of UO3, PuO2 and NpO2 as well as the removal and isolation of technecium from the SNF.

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: A ceramic waste immobilizing material for the encapsulation of high level radioactive waste (HLW), e.g. resulting from the reprocessing of irradiated nuclear fuel. The ceramic waste immobilising material enables waste ions from at least fission products in irradiated nuclear fuel to be dissolved in substantially solid solution form. The ceramic waste immobilising medium has a matrix comprising phases of hollandite, perovskite and zirconolite in which the waste ions are dissolved. The invention also includes a method of immobilizing HLW from reprocessed nuclear fuel assemblies comprising the steps of mixing a liquor containing the HLW with a precursor material comprising oxides or oxide precursors of at least titanium, calcium and barium to form a slurry, drying the slurry, and calcining the dried slurry under a reducing atmosphere to form a powder comprising 30–65 weight % waste.

Abstract: A fuel assembly avoiding the generation of irradiation damage, a Zr alloy used for the same, and a manufacturing method thereof. According to one embodiment, a super-saturated solid-solution Zr alloy powder having a crystal grain size in the range of 1000 nm or less and containing Fe, Ni and Cr is prepared by mechanical alloying, and the alloy powder is subjected to HIP, hot-working, cold-working and final heat-treatment.

Abstract: The core samples of solidified hazardous waste, such as nuclear waste, are extracted from waste material in a drum by inserting rotating tubular core drills into the waste material and then withdrawing the core drills with core samples of the waste material accumulated within the core drills. Preferably, the core samples are retained within plastic tubular retainers which are withdrawn from the core drills and capped. While the rotating tubular core drills are being inserted into the sample, pressurized gas is applied through are annular space between the tubular sample retainers and the walls of the core drills to cool the cutting heads and to expel cuttings away from the end of the drills up to the top surface of the material. In addition, the pressurized gas serves to keep contaminants off the outside surface of the plastic tubular sample containers.

Abstract: Provided is a method for making high-temperature high-performance fuel particles wherein fertile or fissile metal carbides are dispersed in spherical graphite skeletons. That is, a fissile metal salt, such as uranyl nitrate, is added to an aqua-mesophase in alkaline solution, to form a fuel solution. The fuel solution is added to an oil bath to form an emulsion of aqueous pitch-derrived spheres in oil. The emulsion is heated and stirred to drive water from the spheres to dry them into solid spheres which contain the above metal salts. The solid spheres are then heated to between 700-1100 C. to carbonize them and convert the metal salts to metal oxides and then the spheres are further heated to between 2000.degree.-3000.degree. C., to carburize the metal oxides to metal carbides and graphitize the carbon. The resulting fuel spheres are then preferably coated by deposition thereon, of a carbon or carbide coating to contain the future reaction products thereof.

Abstract: Process for preparing a radionuclide generator for producing Tc-99m or Re-188. A clear solution containing a metallic cation and an anion comprising W-188 or Mo-99 is provided. The metallic cation is present in the solution as a dissolved complex of the metallic cation and a complexing agent and/or the anion being present in the solution as a dissolved complex of the anion and a complexing agent. The dissolved complex(es) are decomposed to form a slurry containing a precipitate of the metallic cation and the anion. The precipitate is transferred to an elutable container of a radionuclide generator.

Abstract: According to the invention, the oil is passed through a pulverulent material, such as an earth or clay, in the presence of an acid. The pulverulent material can be placed beforehand on a filter or can be mixed with the oil before filtration. If necessary, the oil is recycled through the filter up to complete decontamination.Application to the radioactive decontamination of oils used in the nuclear industry.

Abstract: An aggregate suspension containing holmium-166 hydroxide and a carrier (such as a particulate ferric hydroxide) is injected into a patient's anesthetized joint (such as a knee joint or hip joint) for the treatment of inflamed synovial tissues such as present in arthritis, especially rheumatoid arthritis. The aggregate suspension is in a range of particle sizes from 1 to 40 microns. The holmium-166-containing suspension treats the synovial tissues, whereby radiation synovectomy takes place.

Abstract: Radiolabeled colloid compositions and a method for the preparation of radionuclide-colloid compositions useful in the treatment of rheumatoid arthritis are disclosed. A radionuclide selected from the group consisting of Sm-135, Ho-166, In-155m, Y-90, Gd-159 La-140, Lu-177, or Yb-175 is sorbed to a previously prepared iron-hydroxide colloid. The radiolabeled colloid compositions are comprised of spherical aggregations containing greater than 50% of the radioactive metal in iron-hydroxide particles. The method produces stable radionuclide iron-hydroxide compositions which are useful in therapeutic procedures such as radiation synovectomy.

Abstract: A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints.

Abstract: In a process for decontaminating radioactively polluted lubricant oil, (a) the lubricant oil to be decontaminated is mechanically filtered, (b) an acid solution of the salts of the elements, the radionuclides of which are to be removed, is added, and (c) a dose of a precipitating agent that cooperates with the elements, the radionuclides of which are to be removed, producing a salt of low solubility, is added, (d) the acid salt solution is intimately mixed with the lubricant oil after step (b), (e) the depositing aqueous phase is discharged after step (b), before step (c), (f) additional intimate mixing is carried out after the dosed admixture of step (c), and (g) finally the precipitation products are separated by centrifugation from the lubricant oil.

Abstract: A process for the embedding or containment of waste materials, especially of radioactive waste materials, by embedding in a ceramic matrix through the intermediary of the chemical precipitation of a hydrosol of the matrix, which is formed through the reaction of a nitrate with ammonia or ammonium hydroxide. In this process, the hydrosol is trickled in a pouring column into a precipitation bath, subsequent to the introduction of the material which is to be embedded, in which the hydrosol particles which are formed during the trickling gelatinize into gel particles. The gel particles are removed from the precipitation bath, washed, dried and finally sintered.

Abstract: A soluble salt (sodium sulfate or sodium borate (Na.sub.2 SO.sub.4 or Na.sub.2 B.sub.4 O.sub.7) contained as the main component in a concentrated radioactive waste liquid generated in the BWR power plant or the PWR power plant is insolubilized and precipitated, sodium hydroxide (NaOH formed in the insolubilization is separated from the precipitate and the radioactive waste liquid slurry containing the precipitate is solidified with a hydraulic solidifying material. Since the separated caustic soda (NaOH) is free of radioactive substances, it can be easily utilized again, and since the radioactive substances are stably fixed in the solidified body, leakage of radioactivity from the solidified body can be greatly reduced.

Abstract: An improved method of disposing of radioactive or hazardous liquid hydrocarbon compositions comprises placing the liquid hydrocarbons in a container and adding an organic ammonium montmorillonite in ratios of between about 1:2 and 3:1, by volume, respectively. The organic ammonium montmorillonite has at least 10 carbon atoms. A polar organic compound having between 1 and about 10 carbon atoms is also preferably added with the montmorillonite. Where the liquid waste material includes 5% or more of water in addition to the liquid hydrocarbon a minus 200 mesh sodium montmorillonite is also preferably added.

Abstract: Disclosed is a method of reducing the volume of a material containing addition polymerizable bonds by contacting the material with sufficient butyrolactone to dissolve the soluble organic material therein and form a slurry. About 0.1 to about 2% by weight, based on the slurry weight, of an addition polymerizable catalyst is added to polymerize and solidify the slurry. About 10 to about 50% by weight, based on total slurry weight, of an ethylenically unsaturated monomer, such as styrene, can be added to aid in the polymerization process. The process is especially suited to filter elements containing radioactive contaminants.

Abstract: A method of decontaminating mixtures of radioactively contaminated water and radioactively contaminated water-immiscible organic liquids to produce a decontaminated organic liquid which can be disposed of in a conventional manner.

Abstract: A simplified internal gelation process for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85.degree. C.) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column.

Abstract: Firm gel structures are formed from hot aqueous radioactive waste solutions containing boric acid by adding powdered magnesium oxide or magnesium hydroxide followed by addition of calcium oxide or calcium hydroxide. Cement may be introduced after addition of the magnesium compound without interfering with subsequent gel reactions. Product rigidity imparted by the gel enables reduction of typical cement usage up to 50% or more in the processing of radioactive boric acid concentrates. This results in more waste being solidified per container, less exothermic heat generation, greater shipping efficiency, and improved resistance to aqueous leaching of radionuclides.

Abstract: A method of removing radioactive waste from oil in which all particulates, radioactive contaminants, and moisture are removed from the oil. Particulate matter is removed from the oil by a combination of filtering and heating. Radioactive contaminants are reacted with chlorine to form salts which are removed by filtration. Moisture is removed by use of a flash tank.

Abstract: A process and an apparatus are, herein, disclosed for producing microspheres of fissile and/or fertile materials with a high degree of sphericity from a feed solution starter containing at least one metal salt selected from among thorium, uranium and plutonium by using as a gelling medium an organic solvent that has a higher density and a greater interfacial tension with water than the feed solution and which is capable of dissolving ammonia.

Abstract: The present invention relates to the treatment of gel materials to remove water therefrom. The invention provides a process for removing water from a gel material by contacting the gel material with an organic liquid and contacting the organic liquid with a gas such that water is taken up by the gas. The invention, in one embodiment, may be used to dry gel materials while maintaining an open porous network therein.

Abstract: Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

Abstract: Microspheres for nuclear waste storage are formed by gelling droplets containing the waste in a gelation fluid, transferring the gelled droplets to a furnace without the washing step previously used, and heating the unwashed gelled droplets in the furnace under temperature or humidity conditions that result in a substantially linear rate of removal of volatile components therefrom.

Abstract: The present invention relates to the treatment of gel materials to remove water therefrom.The invention provides a process for removing water from a gel material by contacting the gel material with a gaseous mixture of an organic compound and a gas. The organic compound, the gas and conditions of contacting are selected such that water is extracted from the gel material and passes into the gaseous mixture.The invention in one embodiment may be used to dry gel materials while maintaining an open porous network therein.

Abstract: The present invention is directed to a method and apparatus for making a population of dense, closely size-controlled microspheres by sol-gel procedures wherein said microspheres are characterized by a significant percentage of said population being within a predetermined, relatively narrow size range. Microsphere populations thus provided are useful in vibratory-packed processes for nuclear fuels to be irradiated in LWR- and FBR-type nuclear reactors.

Abstract: Heat gelable droplets of a suitable liquid feed material are dielectrically heated to the gelling temperature by exposure to microwave radiation during free fall through a heating zone. The gelled microspheres thus produced are caught and collected in a washing liquid. The microwave radiation is provided through the use of a hollow cavity resonator. A vertical tube which is transparent to microwaves extends through the resonator to delimit the processing zone for the free falling droplets. Frequency control means and a reflected radiation measuring device are associated with the resonator and radiation generation means so that the operation of the system may be closely controlled.

Abstract: Apparatus for contacting particles with a fluid includes two tubes having different diameters and each including a straight lower section inclined relative to the horizontal and a straight, vertical upper section, the lower ends of the tubes being joined together. Fluid introduced into the lower ends of the tubes allows particles to drop slowly in the larger diameter tube and fluidizes the same particles in the smaller diameter tube.

Abstract: Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

Abstract: Sorbitol, or another polyalcohol such as erythritol, dulcitol or xylitol, is added to a solution containing uranyl nitrate which may also contain another heavy metal, such as throium or plutonium, prior to preneutralization with ammonia in order to provide a highly viscous solution that can be preneutralized to a great extent without premature precipitation of uranium. The high viscosity makes possible the formation of favorably large drops when the solution is dripped into an ammonia containing bath for external gelification of the drops. According to the pouring apparatus used, the particles after washing, drying and sintering have a diameter between 0.6 and 1.5 mm. The polyalcohol is added to a hydrosol containing from 1.5 to 2 moles per liter of heavy metal, the polyalcohol being added until concentration of one-third mole of polyalcohol per mole of heavy metal is reached. In certain cases up to four moles of ammonium nitrate per liter are added.

Abstract: Nuclear fuel is made by contacting an aqueous solution containing an actinide salt with an aqueous solution containing ammonium hydroxide, ammonium oxalate, or oxalic acid in an amount that will react with a fraction of the actinide salt to form a precipitate consisting of the hydroxide or oxalate of the actinide. A slurry consisting of the precipitate and solution containing the unreacted actinide salt is formed into drops which are gelled, calcined, and pressed to form pellets.

Abstract: Radioactive organic liquids are converted to a form suitable for burial by the process wherein the liquid is contacted with insoluble, swellable polymer particles to form swollen gelled particles which are dispersed in an unsaturated polyester, vinyl ester resin or mixture thereof which is then cured to a solid state with the gelled particles encased therein.

Abstract: A ceramic composition consisting essentially of Pb(Fe.sub.1/2 Nb.sub.1/2)O.sub.3, Pb(Fe.sub.2/3 W.sub.1/3)O.sub.3 and Pb(Zn.sub.1/3 Nb.sub.2/3)O.sub.3 which allows low-temperature sintering and has a high dielectric constant and a good dielectric constant temperature coefficient.

Abstract: An improved polycrystalline semiconducting ceramic composition comprises an alkaline earth metal titanate doped with a hexavalent metal oxide such as (MO.sub.3)(Bi.sub.2 O.sub.3).sub.x where M is tungsten or molybdenum, and x ranges from 0 to 7, which is liquid phase sintered with lead germanate to produce internal insulating boundaries. The composition is fine grained and provides thin-layer, multi-layer capacitors that exhibit high dielectric constant values, low dissipation factors, and low temperature and voltage coefficients of capacitance.

Abstract: A novel ceramic composition exhibiting a solid solution structure of Pb(Fe.sub.2/3 W.sub.1/3)O.sub.3 --Pb(ZrO.sub.3), can be sintered at a low sintering temperature; have a high insulation resistance; have a relatively high dielectric constant in the high dielectric type ceramic dielectrics; have a low dependence of dielectric constant upon temperature, and; have a low dielectric loss.A particular amount of the additives, i.e., MnO, Pb(Mn.sub.1/3 Nb.sub.2/3)O.sub.3, Pb(Mn.sub.1/2 W.sub.1/2)O.sub.3, Pb(Mn.sub.2/3 W.sub.1/3)O.sub.3, Pb(Mn.sub.1/3 Ta.sub.2/3)O.sub.3, Cr.sub.2 O.sub.3 and CeO.sub.2, is added into the composition mentioned above.

Abstract: A dielectric composition for influencing electric fields comprising a dielectric base material having electrically conductive and electrically insulating platelet-shaped particles and stress control devices made therefrom.

Abstract: A dielectric ceramic composition consists essentially of strontium titanate, magnesium titanate, bismuth oxide, titanium oxide, and lead oxide, these components being present in the following compositional proportion when expressed by the formulas, SrTiO.sub.3, MgTiO.sub.3, Bi.sub.2 O.sub.3, TiO.sub.2 and Pb.sub.3 O.sub.4, respectively:______________________________________ SrTiO.sub.3 30.0-60.0 wt % MgTiO.sub.3 2.0-32.0 wt % Bi.sub.2 O.sub.3 10.0-34.0 wt % TiO.sub.2 3.0-15.0 wt % Pb.sub.3 O.sub.4 2.0-20.0 wt % Pb.sub.3 O.sub.4 /MgTiO.sub.3 0.625-10.0 (weight ratio) ______________________________________The composition exhibits high permittivity, small dielectric loss, small dependency of permittivity on temperature, and high dielectric breakdown voltage in combination, so that it makes it possible to produce physically small capacitors with large capacity and high rating voltage. The process for production of the composition is characterized by the use of MgTiO.sub.3 and Pb.sub.3 O.sub.

Abstract: New high voltage insulating compositions are disclosed. The compositions comprise a polymer (e.g. a polysiloxane, epoxide resin or a polymer of one or more olefins or substituted olefins), an antitracking additive (e.g. an alumina hydrate), and certain phosphorus-containing compounds which have been found to provide the compositions with greatly improved resistance to erosion by high voltage stress. The phosphorus-containing compounds include phosphonates, phosphates, phosphites, phosphinates, phosphonites, phosphinites, phosphine oxides and sulfides, and phosphines, and salts and complexes thereof. The phosphorus-containing compound can react in situ with the polymer or other ingredients of the composition.

Abstract: A monolithic ceramic capacitor having buried nickel electrodes is made by forming a paint of alkaline earth zirconates, a boron containing powder and an organic vehicle and binder. Nickel containing films are buried between dried and stacked layers of the paint. The stack is fired in a partial oxygen atmosphere at from 1200.degree. C. to 1400.degree. C. to produce a fully densified ceramic having a dielectric constant of greater than 30 and to provide a nickel electroded monolithic capacitor having a Q of greater than 1000 and a TCC of between .+-.30 ppm/.degree.C. or better.

Abstract: An improved method of disposing of radioactive or hazardous liquid hydrocarbon compositions comprises placing the liquid hydrocarbons in a container and adding an organic ammonium montmorillonite in ratios of between about 1:2 and 3:1, by volume, respectively. The organic ammonium montmorillonite has at least 10 carbon atoms. A polar organic compound having between 1 and about 10 carbon atoms is also preferably added with the montmorillonite. Where the liquid waste material includes 5% or more of water in addition to the liquid hydrocarbon a minus 200 mesh sodium montmorillonite is also preferably added.