摘要:
The invention relates to the nuclear industry, and more particularly to a technique for producing a ceramic nuclear fuel for nuclear reactor fuel rods. A method for producing nuclear fuel pellets with a burnable absorber includes preparing triuranium octoxide with a burnable absorber, preparing a molding powder, compression molding, sintering and polishing. Gadolinium hydroxycarbonate Gd(OH)CO 3 ·xH 2 O (or Gd(CO 3 ) 3 ·xH 2 O) is used as the burnable absorber. The compression molded fuel is sintered in reducing environments (inter alia with the addition of N 2 ), and gases supplied are saturated with water vapour, wherein the humidity of the sintering atmosphere is from 8000-15000 ppm (depending on the amount of burnable absorber), and the sintering temperature is 1650-1750°C. The amount of burnable absorber in the fuel pellets is 1.50-12.00 wt%. During the stage of preparing a homogeneous charge, triuranium octoxide powder and/or triuranium octoxide with gadolinium is added in an amount up to 30 wt% to uranium dioxide powder. The technical result of the invention is an increase in the oxygen coefficient values (the ratio of the number of oxygen atoms covalently bonded with uranium to the number of uranium atoms) in the fuel pellets, thus leading to an increase in thermal conductivity and a reduction in fuel pellet deformation in a nuclear reactor.
摘要:
The invention relates to a process for preparing a powder of an oxide of at least one metal, each metal having an oxidation number of between (III) and (VI). This process comprises, successively and in this order: (a) the reaction, with a compound comprising a hydroxide, of an aqueous solution comprising, for each metal, at least one salt of the cation of said metal, (b) the separation of the precipitate obtained, (c) the bringing of the separated precipitate into contact with an organic protic polar solvent, (d) the elimination of the organic protic polar solvent by drying of the precipitate under vacuum. The invention also relates to a process for manufacturing a pellet of an oxide of at least one metal and also to the powder and pellet obtained according to these processes and to the uses thereof.
摘要:
The invention relates to a method for generating droplets over a variable spectrum of particle sizes, characterized in that it comprises the following steps: impacting a liquid stream onto a substrate at a given relative impact speed; vibrating said substrate at at least one vibration frequency; heating said substrate to a so-called impact temperature such that the liquid film formed by the impact and vibrated is heated to a so-called main temperature so as to form, in a combined manner, so-called main droplets from said film; transporting said droplets via a transfer/braking/sorting system toward a liquid for precipitating the main droplets, said transport being accomplished at a so-called transport temperature, wherein the set of the relative impact speed, vibrating frequency, main temperature, and transport temperature parameters enabling the modulation of the particle size of said formed main droplets, as well as the modulation of the speed thereof. The invention also relates to a device for implementing the method of the invention.
摘要:
The invention relates to a method for preparing an oxalate of one or more actinides, including: precipitating said actinide or coprecipitating the actinides in the form of oxalate particles by contacting an aqueous solution containing the actinide(s) with an aqueous solution of oxalic acid or an oxalic acid salt; collecting the resulting oxalate particles; characterised in that the precipitation or coprecipitation is carried out in fluidised bed. The invention also relates to a method for preparing an oxide, carbide, or nitride actinide oxalate using said method. The invention can be used for processing and recycling nuclear fuel.
摘要:
The invention relates to a method for the production of spherical combustible or fertile material particles from an oxide of the group of the heavy metals uranium, thorium, plutonium, or mixtures thereof. For this purpose, the process steps of producing a base solution of the nitrates of the heavy metal(s), adding at least one first reagent in order to adjust the viscosity of the solution, dropping the solution to form microspheres, at least superficially solidifying the microspheres in an atmosphere containing ammonia, collecting the microspheres in a solution containing ammonia, and subsequent washing, drying and thermal treatment are carried out, wherein urea and/or ammonium carbonate and/or ammonium hydrogen carbonate and/or ammonium cyanate and/or biuret are added to the base solution before adding the first reagent, and the solution thus prepared is heated to a temperature T at 80° ≤ T
摘要:
A process for producing UO 2 powder, comprising the steps of comminuting a uranium-containing metal alloy to produce a uranium-containing metal alloy powder, oxidizing the uranium-containing alloy powder at elevated temperature to produce oxidized metal alloy containing U 3 O 8 and metal impurities, dissolving the oxidized metal alloy containing U 3 O 8 and metal impurities in nitric acid, filtering to produce a uranyl nitrate solution, subjecting the uranyl nitrate solution to solvent extraction to remove remaining metal impurities to produce a purified uranyl nitrate solution, precipitating ammonium diiuranate from said uranyl nitrate solution, and heating said ammonium diiuranate precipitate to produce UO 2 powder.
摘要:
The invention concerns a system for filtering reaction gases coming from a reactor with fluidised bed (10) for converting uranium hexafluoride UF6 into uranium oxide, comprising first filtering means (13), with automatic declogging, allowing said reaction gases to pass through and retaining the pulverulent intermediate compound UO2F2 which is formed during conversion. It further comprises second filtering means (18) for allowing said reaction gases to pass through and retaining the UO2F2 compound in the event of leakage owing to malfunction in the first filtering means (13).
摘要:
A rotary kiln, particularly for producing uranium dioxide from uranium hexafluoride, has an inlet arrangement (1) and a heated rotatable barrel (14). Uranium hexafluoride and steam react together in the inlet arrangement (1) to form uranyl fluoride which is fed into the barrel (14) by the aid of a rotating scroll feed device (17). In the barrel, the uranyl fluoride reacts with a counterflow stream of steam and hydrogen to produce the uranium dioxide. A porous metal or ceramic filter (28) closely surrounds the scroll feed device (17) to remove particles from kiln-produced gases. The filter is maintained in a clean condition by the scraping action of a number of helical blades forming part of the scroll feed device (17). The uranium dioxide powder produced by the kiln may be processed to form nuclear fuel pellets.