Abstract: A method of making finely particulate ammonium perchlorate which comprises establishing a two-phase liquid system in which the upper phase is a concentrated solution of ammonium perchlorate and the lower phase is a liquid which is immiscible with the upper phase solvent and a non-solvent for ammonium perchlorate. Precipitation of ammonium perchlorate from the solution into the non-solvent is effected by either cooling the solution or evaporating the solvent thereof while subjecting the system to ultra-sonic vibrations. Fine ammonium perchlorate particles collect in the non-solvent phase and are recovered therefrom.

Abstract: A process for making nitrogen trifluoride by introducing gaseous fluorine azide into a reaction zone containing a fluorinating agent selected from nitrosyl fluoride and chlorine trifluoride.

Abstract: Process and apparatus for producing ammonium diuranate (ADU) from uranium hexafluoride (UF.sub.6) wherein gaseous UF.sub.6 is first hydrolyzed, then partially neutralized with aqueous ammonium hydroxide to a pH of from 5 to 6, the resultant solution is conveyed to a precipitation vessel wherein it is admixed with additional aqueous ammonium hydroxide to a pH of from 9.8 to 10.

Abstract: A method is disclosed for eliminating carbon from nuclear fuel elements in the reprocessing thereof in a closed system wherein such carbon is caused to combine with hydrogen to form methane in an attack zone, and the methane is then caused to flow from the attack zone to a regeneration zone where it is cracked into carbon and hydrogen.

Abstract: Uranium is separated from mixed oxides of thorium and uranium by a pyrometallurgical process in which the oxides are mixed with a molten chloride salt containing thorium tetrachloride and thorium metal which reduces the uranium oxide to uranium metal which can then be recovered from the molten salt. The process is particularly useful for the recovery of uranium from generally insoluble high-density sol-gel thoria-urania nuclear reactor fuel pellets.

Abstract: Ceramic nuclear fuel is reprocessed through a method wherein the fuel is dispersed in a molten eutectic mixture of at least two alkali metal nitrates and heated to a temperature in the range between 200.degree.C and 300.degree.C. That heated mixture is then subjected to the action of a gaseous stream containing nitric acid vapors, preferably in the presence of a catalyst such as sodium fluoride. Dissolved fuel can then be precipitated out of solution in crystalline form by cooling the solution to a temperature only slightly above the melting point of the bath.

Abstract: 1. A novel process for preparing beryllium hydride and aluminum hydride which comprises;A. adding a solution of beryllium borohydride to a solution of lithium aluminum hydride such that the ratio of lithium aluminum hydride to beryllium borohydride on a gram mole basis ranges from about 2 to about 5 and precipitating beryllium hydride in the resulting mixture, the solvent for said lithium aluminum hydride and beryllium borohydride being a liquid material inert to the reactants and products and dissolving said beryllium borohydride and lithium aluminum hydride but being a substantially non-solvent for beryllium hydride,B. separating said solid beryllium hydride from the reaction mass,C. stripping said solvent from the residual reaction mixture,D. heating the resulting substantially dry product mass at an elevated temperature of from about 45.degree. to about 140.degree. C. for a period of from about 0.25 to about 24 hours, andE.

Abstract: An ultra-high strength steel composition of matter having a substantially martensitic matrix with a dispersion therein of a critical amount of metal oxide particles and characterized by increased resistance to environmental stress corrosion cracking. The metal oxide particles are selected from the group consisting of CaO, BaO, MgO, SrO and mixtures thereof, in the range of 0.1 to less than 3 mole percent. A powder metallurgy process to produce articles of manufacture from the composition of matter is disclosed.

Abstract: A seal member is provided with an improved combination of oxidation resistance, fluid erosion resistance, reduced thermal conductivity and low flow stress at elevated temperatures through a plurality of metallurgically bonded metal alloy powder particles in the size range substantially of about +140 to about -270 ASTM (U.S. Standard Sieve) the metal particles being metallographically distinguishable and consisting essentially of, by weight, 15 - 35% Cr, about 8 to 20% Al, up to 5% of elements selected from Y, Hf and the rare earth elements, with the balance selected from Fe, Co and Ni, the member having a density in the range of about 65 - 90% of theoretical density.

Abstract: A method of producing a high strength, highly ductile titanium base article is provided which comprises coating pre-alloyed metal particles with an iron containing compound which is capable of being converted to elemental iron particles, converting this iron containing compound to elemental iron particles, mixing the iron particles and pre-alloyed metal particles with titanium base particles, forming this mixture of particles into the desired article, heating the formed article under vacuum conditions to a temperature sufficient to cause the constituent particles of the article to become diffused together, and cooling the article to produce a sintered titanium base article.

Abstract: Metal hydroxides such as Fe(OH).sub.2, Fe(OH).sub.3 and Sn(OH).sub.2 are prepared in the form of spherical particles of uniform and controlled size suitable for tagging with a radioactive element such as technetium-99m. Aqueous suspensions of such tagged particles are useful in scintigraphy as lung scanning agents.

Abstract: Molybdenum alloys containing at least two metallic element components which form a molten alloy which dissolves appreciable Mo during liquid phase sintering may contain additives selected from Co, Mn, Cr, Ru, Zr, Ti, Hf, Re, refractory metals, and metalloids to obtain desired properties for certain applications. Many of these additives are particularly effective in shaping members.

Abstract: A process for the treatment of irradiated fissile material in solution in nitric acid in which tributylphosphate diluted to less than 7% by volume with an inert diluent is contacted with the nitric acid solution and backwashed with sulphuric acid.

Abstract: The material consists of a mixture of silver and 1.0 to 20 weight per cent of lanthanum, strontium chromite of the formula La.sub.1.sub.-x Sr.sub.x CrO.sub.3, where the values of x lie between 0 and 1.0. The addition of 2.5 to 20 weight per cent of cadmium oxide further improves the electrical contact material by providing anti-weld properties to the contact interface. The electrical contacts are formed from the contact material by powder metallurgy techniques.

Abstract: A process for producing selenium homogeneously doped with a metal. The process comprises mixing the metal with selenium, melting the selenium and mixing the resulting melt in the absence or substantial absence of oxygen or with the extraction of any oxygen or oxide contained in the melt so as to produce selenium homogeneously doped with the metal.

Abstract: An electrically conducting artefact is produced by heating a silicon nitride artefact to a temperature high enough to decompose part of the silicon nitride to silicon but not high enough to evaporate the silicon which is formed, the heating taking place either in an environment which is inert to silicon or in a carbon containing environment which reacts with the silicon formed to give silicon carbide. Such an artefact has electrical conductivity properties which may, for example, be retained after heating at about 600.degree.C in air for several hours.

Abstract: Titanium diboride is composited with about 11 to 13 per cent by weight of copper and about 2 to 4 per cent by weight of nickel, preferably by mixing the constituents in powdered form, heating the mixture to about 2000.degree.F, and then hot pressing at a pressure of about 3000 psi and a temperature of about 2650.degree.F. The titanium diboride-copper-nickel composite composition possesses execellent strength and non-sparking properties useful in the fabrication of mining tools and implements.

Abstract: A method of providing sintered and diffused metal coatings of finely divided metallic material on a metal base, such as a steel strip or panel, by forming a molten film of one or more higher fatty acid amides having a carbon chain length from about 8 to 18 carbon atoms on a clean surface of the metal base which is preferably heated to a temperature above the melting point of the fatty acid amide film, applying uniformly on the molten amide film an amount of a finely divided metallic material, such as powdered Monel metal or nickel, in excess of that which settles into the film and is held thereby and removing the excess metal powder after the amide film has solidified, and heat treating the metal base having the coating of amide and metal powder thereon in a non-oxidizing reducing atmosphere at a temperature and for a period sufficient to effect bonding of said finely divided metallic material with each other and with said metal base to form a uniform firmly adherent metal coating.

Abstract: The process of making oxygen difluoride which comprises subjecting alkali metal hyponitrite containing 2-5 oxygen atoms, at temperature not substantially above 40.degree.C., to the action of elemental fluorine in quantity and for a time sufficient to effect reaction of the fluorine with a substantial amount of hyponitrite to form a substantial quantity of oxygen difluoride, and recovering oxygen difluoride.

Abstract: A method of simultaneously obtaining separate enriched fractions of .sup.235 U and .sup.238 U from isotopic mixtures thereof with the use of an ion exchange column by passing a liquid body containing the isotopic mixture through the column. The uranium as it is passed through the column is present as a U(IV) coordination compound with a ligand at different valent states and is followed by an eluant and forms a band which travels through the column, the front and rear portions of which are respectively enriched in one of the isotopes and depleted in the other.