Abstract: For making ceramic or oxidic layers (CL/OL) on substrates (S), the method according to the invention therefore provides that following application (I) and drying (II) of a suitable precursor (P) the formed precursor layer (PLD) is gassed (III) with a moist reactant gas (RG) for conversion into a corresponding hydroxide or complex layer (HL) and then thermally treated (IV) for forming a ceramic or oxidic layer (CL/OL). For the alternative production of other chalcogenidic layers of increased material conversion additional gassing is carried out with a reactant gas containing chalcogen hydrogen. Metallic layers may alternatively be made by use of a reducing reactant gas. The methods in accordance with the invention may be used wherever surfaces, even those of shaded structures, must be protected or modified or provided with functional layers, particularly in solar and materials technology.

Abstract: Several new and useful compositions of rare earth oxides and mixtures of rare earth oxides are made into strong flexible fibrous textiles and strands. By varying the mixtures of rare earth metal oxides that make up the textiles and strands, the emission spectra can be matched to the absorption spectra of a variety of semiconductor photovoltaic cells. Furthermore, the addition of between 1-10 mol % of thorium oxide to the rare earth metal oxide fibers inhibits microcrystalline grain growth at high temperatures.

Abstract: Several new and useful compositions of rare earth oxides and mixtures of rare earth oxides are made into strong flexible fibrous textiles and strands. By varying the mixtures of rare earth metal oxides that make up the textiles and strands, the emission spectra can be matched to the absorption spectra of a variety of semiconductor photovoltaic cells. Furthermore, the addition of between 1-10 mol % of thorium oxide to the rare earth metal oxide fibers inhibits microcrystalline grain growth at high temperatures.

Abstract: The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets. As a result, the temperature in the center of the fuel rod can be significantly reduced, and the discharge amount of gases generated on the nuclear fission can be efficiently reduced.The present invention also provides a method of manufacturing the above-described nuclear fuel pellets.

Abstract: The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets. As a result, the temperature in the center of the fuel rod can be significantly reduced, and the discharge amount of gases generated on the nuclear fission can be efficiently reduced.The present invention also provides a method of manufacturing the above-described nuclear fuel pellets.

Abstract: The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets. As a result, the temperature in the center of the fuel rod can be significantly reduced, and the discharge amount of gases generated on the nuclear fission can be efficiently reduced.The present invention also provides a method of manufacturing the above-described nuclear fuel pellets.

Abstract: The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets. As a result, the temperature in the center of the fuel rod can be significantly reduced, and the discharge amount of gases generated on the nuclear fission can be efficiently reduced.The present invention also provides a method of manufacturing the above-described nuclear fuel pellets.

Abstract: A process for producing high quality optical glass from fluoride glasses comprising preparing a melt of the glass and then cooling the melt in-situ inside the melt crucible. The in-situ quenching technique can be improved by narrowing the temperature range between the liquidus temperature and the glass transition temperature of the glass. The stability of the fluoride glass can be increased and the liquidus temperature of the glass can be lowered by doping the glass with a chloride dopant. Thorium tetrafluoride can be added to the chloride-doped glass in order to increase the chemical stability of the glass.

Abstract: ThF.sub.4 --BeF.sub.2 glasses of specified composition exhibit sufficiently low high-temperature viscosity and melt stability to be useful for the fabrication of optical devices for ultraviolet or infrared light transmission. The low melt viscosity renders the glasses suitable as host materials for rare earth and transition metal dopants so that they can be used for optical devices such as lasers and optical filters.