Abstract: In order to produce aluminium oxide beads, an acid aluminium oxide sol or an acid aluminium oxide suspension is converted into droplets by a vibrating nozzle plate and pre-solidified after the formation of a bead shape by laterally blowing gaseous ammonia and then coagulated in an ammonia solution.

Abstract: To manufacture spherical particles out of liquid phase with a narrow grain spectrum using melting temperatures of up to 1500.degree. C. by generating droplets by means of vibrating nozzles, the liquid phase, the nozzle and the drop distance for the droplets are maintained at a constant temperature of 1.degree. to 10.degree. C. above the melting temperature of the liquid phase until the spherical shape of the falling droplets has stabilized. The particles must then be abruptly chilled.

Abstract: A device for the thermal treatment of organic substances and of inorganic substances contaminated with organic substances which makes a high throughput possible. The reactor contains several bottoms provided with perforations with ceramic ball sections which can be moved separately.

Abstract: The encapsulation of a photovoltaic element is described in which the outer surface is provided with a two layer protective film comprising a carbon film and a dielectric silicon compound film.

Abstract: There is needed a process and an apparatus for the pyrolytic decomposition of halogen and/or phosphorus containing organic materials, particularly those which are radioactive, in which no corrosive secondary products, minimal amounts of waste gas, small amounts of dust and conditionable active solid waste form. This is accomplished by mixing the materials in an over stoichiometric ratio with basis compounds and introducing them from above in the form of a suspension into a fixed bed reactor which is charged with mechanically agitated substantially spherical ceramic structures.

Abstract: Substantially isotropic spherical fuel and absorber elements for high temperature reactors are produced by molding corresponding fuel particles and graphite molding compositions. There is used as graphite molding powder a mixture of graphitized granules of coke and a hardenable resin binder. There are first produced in steel dies at 80.degree. to 120.degree. C. half shells and a nucleus with a pressed density of 1.0 to 1.4 g/cm.sup.3 followed by molding in a further steel die to the final format.

Abstract: A contact system for thin film solar cells, which guarantees that charge carrier transport without a barrier layer takes place from the semiconductor layer facing the light source to the front contact in such a manner that, among others, long term negative influences by the front contact on the semiconductor layer will not take place. To this end the front contact is rendered passive against the semiconductor layer by modifying its chemical potential, at least in the actual contact area, to be matched to the chemical potential of the semiconductor layer, or by forming a chemically inert system acting as a reaction barrier between the front contact and the semiconductor layer.

Abstract: There is described a process for the production of high temperature resistant, high density ceramic molded articles at a temperature above 1300.degree. C. and at high pressure in a mold. For this purpose, the blank is heated outside the mold, transferred with a die at 1 to 10 m/sec into the cold mold, compressed there and ejected in the pressing direction. Thereby, the residence time in the mold must be less than 3 msec and the sum of the transport time of the blank from heating up to the mold and the residence time in the mold so regulated that the temperature drop between the nucleus of the blank and the surface of the blank does not exceed 150.degree. C.

Abstract: There are known molded bodies for the safe, long time fixation of radioactive and toxic wastes which have a matrix of graphite and inorganic binding agent, preferably nickel sulfide. An increased resistance to leaching is obtained with molded bodies that have a waste containing nucleus and a waste free shell made of the same graphite matrix.

Abstract: There is described a process for the production of ceramic fuel pellets which contain fission and/or fertile material in oxidized form, by heating porous green fuel pellets in a reducing atmosphere to a temperature below 2500.degree. C., molding in a die, ejecting from the die and cooling the finished pellets. Thereby the heating and cooling is carried out stepwise whereby the heating and cooling speed below 1200.degree. C. is less than 30.degree. C./second and above 1200.degree. C. is greater than 30.degree. C./second.

Abstract: For the transportation and long time storage of radioactive waste, especially of spent fuel elements, in suitable geological formations, there are needed multi-layered containers which guarantee a tight sealing even for a long period of time, are corrosion resistant to salt liquors, without being too expensive and too heavy. This is obtained by using for the individual layers of the container different metals or metal alloys which, from the outside inwardly, always are more noble (positive) in the electromotive (electrochemical) series.

Abstract: For the longtime fixation of radioactive and toxic waste there are used molded bodies made of graphite with nickel sulfide as a binding agent. The molded bodies show especially good properties if the nickel sulfide is in the form of Ni.sub.3 S.sub.2.

Abstract: For the production of plate shaped fuel elements for material testing and research reactors with highly enriched uranium recently there has been needed U.sub.3 O.sub.8 fuels which have a high density, high strength and a small open porosity. Such fuels are obtained if U.sub.3 O.sub.8 powder produced in known manner is first compressed mechanically to molded bodies of any shape, then processed to a granulate having a size of fuel grains below 200.mu. and subsequently sintered to high density particles, preferably at 1370.degree..+-.50.degree. C.

Abstract: Previously the conditioning of radioactive wastes took place through binding the waste in a matrix of glass, silicon carbide, cement, bitumen, synthetic resin or vitreous carbon. These processes have many disadvantages, particularly the matrix has poor heat conductivity, insufficient resistant to extraction or poor heat resistance and radiolysis effects. A remedy is provided through a carbon matrix in which there is employed as the starting material graphite which is molded with a binder at a temperature above 100.degree. C. There have particularly proven good as the binder sulfur in admixture with nickel powder from which nickel sulfide forms.

Abstract: A process for producing ceramic fuel pellets for nuclear reactors containing the fissionable material and/or fertile material in the form of the oxide or carbide by heating to a temperature above 1300.degree. C. the crude molded fuel articles compacted to 30 to 60% of theoretical density at room temperature, molding in a die and ejection from the die wherein the heating, molding and ejection take place in a vacuum and the molding and ejection take place within 3 to 300 milliseconds.

Abstract: Coated nuclear fuel particles are produced by batchwise deposition of several pyrolytic carbon and/or silicon carbide layers on fuel particles wherein the first layer is a porous pyrolytic carbon layer and wherein the coated particles are subsequently sieved and/or sized. The process comprises fractionaling all of the coating batches according to the geometric density by the hydrostatic method of weighing by buoyancy after placing all batches in heavy liquids and selecting for further working up into fuel elements only the particle fraction which has a geometric density whose boundary value deviates from the average density by less than .+-.20%.

Abstract: There is disclosed a process for the production of solid particles of bioinjurious waste, e.g., radioactive concentrates, wherein a liquid, and in a given case a binder containing waste is divided into drops and supplied energy in a gaseous medium, the liquid is evaporated and the drops form solid particles. There is supplied carrier free energy to at least partially vaporize the liquid of the drops, in a given case under reduced pressure and in a given case with a binder forming solid particles from the drops.

Abstract: There are provided pressed spherical fuel elements for high temperature reactors made of a graphite matrix with separate embedded coated fuel and fertile material particles wherein the fuel elements comprise 3 concentric layers including a graphite nucleus or core (1) which only contains fertile material particles (4), this graphite nucleus (1) is surrounded by a graphite zone (2) which only contains the fuel particles (5) and this is encased in a shell (3) of pure graphite, the same graphite material being present in all three layers.

Abstract: Fuel, fertile material or absorber material containing particles for high temperature fuel elements are coated in a fluidized bed by heating the particles and fluidizing through carrier gas preheated to the desired temperature. The coating gas, having a higher velocity than the carrier gas causing fluidizing, is blown into the fluidized particle bed from one or more nozzles from above counter to the flow of the carrier gas. The nozzles end above the fluidized layer.

Abstract: A fuel element for high temperature reactors with good heat transfer from the fuel charge to the structural graphite is obtained by seating the fuel charges without a gap in the bores of the structural graphite.