Abstract: This invention relates to an impact absorber for containers for nuclear fuels, radioactive products and/or dangerous chemical substances and used either for transporting or for storing said materials.Said impact absorber is constituted by two convex shells fixed to the ends of the container by means of frusto-conical flanges and clamping half-rings, which are joined together by nuts and bolts.

Abstract: A device is disclosed for applying a head fitted with a measuring instrument to a nuclear fuel bar, the device comprising a casing containing a drilling tip and means for stopping the drilling tip as a bore has been formed through the bar plug and an instrument, such as a pressure gauge for measuring the pressure of the released fission gases, or another instrument adapted to measure a parameter of interest.A method for applying a head containing a measuring instrument to a nuclear fuel bar is also described.

Abstract: Ceramic pellets, which may have, or not, nuclear fuel materials embedded therein, are formed by first preparing a gel by precipitation of metallic salts from solutions of their compounds at a concentration of at least 10 grams per liter, said solutions being added dropwise to a coagulation bath which contains, for example, ammonium or sodium hydroxide, whereafter the precipitated gel are fired, in one or two stages, to precondition them prior to the compaction to form the final pellets which are subsequently sintered at an appropriate temperature.

Abstract: A method is disclosed for producing solid materials in form of microspheres or spherules for a number of applications, such as nuclear fuel, catalyst, fluid beds for fluidization and other like applications. An inert gas shield is provided to surround the droplets of liquid from which the microspheres shall be originated so as to prevent a premature reaction of such droplets with the reactive gas. Provision is made for renewing the braking foam placed over the liquid reactive bath and the reactive gas is supplied in the form of a blade-like stream so as to improve the contact time and intensity between the droplets and the reactive gas.

Abstract: In a method for reprocessing irradiated nuclear fuels, the fuel to be reprocessed is dissolved in a fused-salt bath while absolute sulfuric acid is added dropwise to said bath, plutonium sulfate is thermally converted into the corresponding oxide, the uranium oxide is electrolytically deposited from the fused-salt bath as the electrolyte, the melted salts are recycled to the starting end of the process and the fission products and the melted salts are conditioned for final disposal.

Abstract: An apparatus is disclosed for producing solid materials in form of microspheres or spherules for a number of applications, such as nuclear fuel, catalyst, fluid beds for fluidization and other like applications. An inert gas shield is provided to surround the droplets of liquid from which the microspheres shall be originated so as to prevent a premature reaction of such droplets with the reaction gas. Provision is made for renewing the braking foam placed over the liquid reactive bath and the reactive gas is supplied in the form of a blade-like stream so as to improve the contact time and intensity between the droplets and the reactive gas.

Abstract: A process for the production of microspheres of thorium oxide, uranium oxide or plutonium oxide and mixtures thereof, containing carbon. The microspheres are prepared by first forming an aqueous alkaline solution of a salt of said metals which will precipitate to a solid form in a concentrated alkaline medium together with an alkaline polymerizable organic monomer and carbon, thereafter dripping this solution into a concentrated alkaline medium wherein metal hydroxide is precipitated out and said monomers polymerized to thereby form said microspheres. The precipitated metal compounds with polymerized monomer and carbon are washed to remove unwanted ions and dried by various methods such as air currents, infrared lamps, high frequency microwaves or preferably by azeotropic distillation whereby the washed particles are dispersed in an organic liquid immiscible with water which is then boiled off. Simple liquids include 1,1,1-trichloroethane, carbontetrachloride and xylene.

Abstract: In the recovery of plutonium from irradiated nuclear fuel elements especially those coming from fast nuclear reactors, the improvement consisting in that the spent nuclear fuel elements are subjected to the action of a molten nitrate bath (mixed nitrates of alkali metals or alkaline earth metals), whereafter the plutonium thus obtained is further decomposed in a nitrate bath at a higher temperature, then the plutonium is recovered and a further thermal decomposition of the remaining material at a still higher temperature enables the uranium to be recovered. The recovery of plutonium requires the action of the nitric vapors, the recovery of uranium does not. Molten nitrates can likewise be recovered and recycled.

Abstract: In the preparation of microspheres of nuclear fuel by feeding droplets of an aqueous solution of a salt of a metal constituting the nuclear fuel that is precipitated by a basic medium and a resin that increases in viscosity in the presence of an alkali into an aqueous alkaline solution so that spheroids are formed therefrom which are then dried and calcined, the geometrical properties of those spheroids are controlled by thermostating the feed solution so that the droplets which are fed into the alkaline solution have a predetermined temperature.

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.