Abstract: Embodiments of a fluidized bed fluorination reactor are provided, as are embodiments of a fluidized bed reactor and embodiments of a fluorination method carried-out utilizing a fluidized bed fluorination reactor. In one embodiment, the fluidized bed fluorination reactor includes a source of fluorine gas, a reaction vessel, a windbox fluidly coupled to the source of fluorine gas, and a conical gas distributor fluidly coupled between the reaction vessel and the windbox. The conical gas distributor has a plurality of gas flow openings directing fluorine gas flow from the windbox into the fluorination reaction vessel during the fluorination process.

Abstract: The invention relates to the use of a compound of the formula KmgF3 to trap metals in the form of fluorides and/or of oxyfluorides in a gaseous or liquid phase. It also relates to a compound of the formula KMgF3 which has a surface area at least equal to 30 m2/g and at most equal to 150 m2/g and also to its methods of preparation. The invention notably finds application in the nuclear industry, in which it can advantageously be used to purify uranium hexafluoride (UF6) present in a gaseous or liquid stream, with regard to metal impurities which are also present in this stream.

Abstract: A method for converting depleted uranium tetrafluoride (UF4) to triuranium octaoxide (U3O8), and producing sulfur tetrafluoride, using a two step process. The first step uses heat and a mixture of the uranium tetrafluoride and an alkaline compound, either an alkaline oxide or an alkaline hydroxide, to produce U3O8 and a water-soluble metal halide. The second step uses heat, sulfur and a halogen to produce sulfur tetrafluoride and triuranium octaoxide.

Abstract: Systems for treating material are provided that can include a vessel defining a volume, at least one conduit coupled to the vessel and in fluid communication with the vessel, material within the vessel, and NF3 material within the conduit. Methods for fluorinating material are provided that can include exposing the material to NF3 to fluorinate at least a portion of the material. Methods for separating components of material are also provided that can include exposing the material to NF3 to at least partially fluorinate a portion of the material, and separating at least one fluorinated component of the fluorinated portion from the material. The materials exposed to the NF3 material can include but are not limited to one or more of U, Ru, Rh, Mo, Tc, Np, Pu, Sb, Ag, Am, Sn, Zr, Cs, Th, and/or Rb.

Abstract: The present invention provides a two-step process for producing nuclear grade, active uranium dioxide (UO2) powder in which the first step comprises reacting uranium hexafluoride (UF6) with steam in a flame reactor to yield uranyl fluoride (UO2F2); and the second step comprises removing fluoride and reducing UO2F2 to uranium dioxide (UO2) in a kiln under a steam/hydrogen atmosphere. The two-step process, each step separated by a positive sealed valve means to prevent gas, particularly H2 flow back, tightly controls the exothermicity of the reaction, which allows for a very tight temperature control which controls the growth of the particles and results in UO2 powder that is active and of consistent morphology.

Abstract: The invention is directed to a method by exposing at least a portion of a luminescent coating disposed on a surface of an article to ultraviolet light at one or more preselected wavelengths causing said luminescent coating to exhibit a luminescence spectrum, the luminescence spectrum exhibiting a plurality of intensity peaks that have been predetermined to create a standard; determining the intensity of at least two peaks in the luminescence spectrum of the coating; determining a peak intensity ratio of the at least two peaks; comparing the peak intensity ratio determined with the standard; and, classifying the article according to whether or not the peak intensity ratio does or does not match the standard; wherein the luminescent coating is a particulate luminescent composition comprising a rare earth doped fluoride represented by the chemical formula REx(CaaSrbBac)1?xF2+x?2yOy wherein RE represents a three-valent rare-earth element, 0.005?x?0.20, and 0?y?0.

Abstract: The invention provides a series of techniques for processing uranium containing feed materials such as uranium ores, reprocessed uranium, uranium containing residues and uranium containing spent fuel. The processes described involve fluorination of uranium containing material, separation of the uranium containing material from other materials based on ionization thereof with the non-ionized fluorine containing material being recycled. Metallic uranium and/or plutonium and/or fission products may result. The technique offers advantages in terms of the range of materials which can be reprocessed and a reduction in the number of complexity of stages which are involved in the process.

Abstract: The invention provides a series of techniques for processing uranium containing feed materials such as uranium ores, reprocessed uranium, uranium containing residues and uranium containing spent fuel. The processes described involve fluorination of uranium containing material, separation of the uranium containing material from other materials based on ionization thereof with the non-ionized fluorine containing material being recycled. Metallic uranium and/or plutonium and/or fission products may result. The technique offers advantages in terms of the range of materials which can be reprocessed and a reduction in the number of complexity of stages which are involved in the process.

Abstract: A method of declogging at least one filter of a plant for manufacturing uranium oxide from uranium hexafluoride, including separating, from the wall of the filter, uranium oxyfluoride particles deposited, by a stream of inert gas such as nitrogen, injected into the filter, in a counter-currentwise direction to the flow of hydrofluoric acid.

Abstract: A substance in a condensed state, for example a powdered solid, is in continuous movement in the longitudinal direction (6) of a furnace (4, 5). A reactive gas mixture is brought into contact with the substance in the condensed state. A plurality of samples of the gaseous mixture are removed at a plurality of reference points (14) spaced apart from one another along the longitudinal direction (6) of the furnace (4, 5); each of the gas samples is analyzed outside the furnace to determine the composition of the gas mixture and for each point (14), the extent of a chemical reaction between the condensed substance and the reactive gas mixture is deduced from the composition of the gas mixture at each of the reference points (14). In particular, the apparatus comprises a sampling and injection rod (10) introduced into the furnace (4, 5) and disposed in its longitudinal direction (6).

Abstract: Fluorine or a fluorine compound is subjected to a reaction with a spent oxide fuel to produce fluorides of uranium and plutonium, and recovering the fluorides using a difference in volatility behavior. The method includes steps of: subjecting a mixture of UO2 and PuO2 with hydrogen fluoride mixed with hydrogen to HF-fluorinate uranium and plutonium into UF4 and PuF3; subjecting UF4 and PuF3 with a fluorine gas to F2-fluorinate uranium and plutonium into UF6 and PuF6; and fractionating UF6 and PuF6 using a difference in phase change of obtained UF6 and PuF6, removing a part of UF6, and volatilizing the remaining UF6 and PuF6 at the same time. By such a reprocessing method, PuF4 hard to undergo a reaction is prevented from being formed as an intermediate fluoride, the material of a reactor is hard to be corroded, and a consumption of expensive fluorine gas is reduced.

Abstract: Fluorine or a fluorine compound is subjected to a reaction with a spent oxide fuel to produce fluorides of uranium and plutonium, and the fluorides are recovered using a difference in volatility behavior. The spent oxide fuel is subjected to a reaction with an HF gas, whereby uranium, plutonium and most impurities are converted into solid fluorides having low valences or remained as oxides to inhibit volatilization thereof, and then in an F2 fluorination step, the HF fluorination product is subjected to a reaction with a fluorine gas in two stages: one at a low temperature and the other at a high temperature, whereby a certain amount of gaseous uranium and volatile impurities are separated with plutonium kept in a solid form in the first stage, and mixed fluorides of remaining uranium and plutonium are fluorinated into hexafluorides at the same time in the second stage. By such a reprocessing method, plutonium enrichment can be adjusted, uranium and plutonium can be purified, and steps are simplified as well.

Abstract: The invention provides a method of separating uranium from at least fission products in irradiated nuclear fuel, said method comprising reacting said irradiated nuclear fuel with a solution of ammonium fluoride in hydrogen fluoride fluorinating said reacted irradiated nuclear fuel to form a volatile uranium fluoride compound and separating said volatile uranium fluoride compound from involatile fission products. The invention thus provides a reprocessing scheme for irradiated nuclear fuel. The method is also capable of reacting, and breaking down Zircaloy cladding and stainless steel assembly components. Thus, whole fuel elements may be dissolved as one thereby simplifying procedures over conventional Purex processes.

Abstract: The method of determining the extent to which a nickel structure has been attacked by a halogen containing gas to which it has been exposed which comprises preparing a quantity of water substantially free from dissolved oxygen, passing ammonia gas through a cuprammonium solution to produce ammonia substantially free from oxygen, dissolving said oxygen-free ammonia in said water to produce a saturated aqueous ammonia solution free from uncombined oxygen, treating at least a portion of said nickel structure of predetermined weight with said solution to dissolve nickel compounds from the surface of said structure without dissolving an appreciable amount of said nickel and analyzing the resulting solution to determine the quantity of said nickel compounds that was associated with said said portion of said structure to determine the proportion of combined nickel in said nickel structure.

Abstract: The conversion apparatus comprises in succession: a reactor provided with injectors of UF.sub.6, steam, and nitrogen so as to cause UO.sub.2 F.sub.2 to be formed by hydrolysis; a rotary tubular pyrohydrolysis furnace for transforming UO.sub.2 F.sub.2 into uranium oxide, and provided with heaters distributed in at least five zones; and a tail end for conditioning the oxide powder. The injectors comprise three concentric nozzles connected respectively to inlets for UF.sub.6, nitrogen, and steam, UF.sub.6 being fed to the central nozzle and nitrogen being injected between UF.sub.6 and steam.

Abstract: Processes for the removal of technetium from contaminated uranium hexafluoride containing technetium, typically as technetium-99 (.sup.99 Tc) in nominal chemical forms are provided. The processes involve contacting the contaminated liquefied uranium hexafluoride with a metal fluoride, typically magnesium fluoride (MgF.sub.2), for a period of time sufficient for the technetium to become adsorbed onto the metal fluoride thereby producing a purified uranium hexafluoride liquid; and removing the purified uranium hexafluoride liquid from the metal fluoride having adsorbed technetium.

Abstract: A process for the recovery of chemical values, particularly uranium, nickel and/or radionuclides from process equipment theretofore employed in a uranium hexafluoride isotope enrichment cascade. Preferably, the process is carried out, in situ, at subatmospheric pressure employing the existing process equipment from which the chemical values are to be recovered. In one aspect, the process includes recovery of uranium values employing a gaseous fluorinating agent at subatmospheric pressure, followed by recovery of nickel values employing a gaseous reactant comprising a mixture of carbon monoxide and a promoter, preferably hydrogen sulfide and at subatmospheric pressure.

Abstract: A single furnace loading cycle method for sintering at least one product. The method comprises the steps of placing at least one product into a ventable/sealable box, which box is placed inside a furnace. The box is vented inside the furnace at a first temperature range, and then the box is sealed with the at least one product inside the box in a second temperature range, wherein the second temperature range is higher than the first temperature range, and wherein the step of sealing occurs after the step of venting without removing the box from the furnace.

Abstract: Uranium fluoride compounds, in which the uranium is preferably present in the tetravalent or higher valency state, are reacted with a strong mineral acid, to yield a gaseous phase of hydrogen fluoride and a precipitate that is a uranium salt of the mineral acid. The precipitate can be subjected to thermal decomposition to recover the mineral acid and to obtain an oxide of uranium. The process provides an economical way of obtaining hydrogen fluoride from byproduct depleted UF.sub.6.

Abstract: A method of purifying a UF.sub.6 gas stream which comprises irradiating the UF.sub.6 gas stream with laser radiation in a vessel in order to selectively convert fluoride impurities in the gas stream to involatile products, removing the purified UF.sub.6 gas stream from the vessel and separately removing the impurities from the vessel.

Abstract: An apparatus and method for producing a product, such as hydrogen halide gas or sulfuric acid, in a regenerator furnace subsystem from a waste containing a non-gasifiable impurity. The method of the invention includes directing a waste, containing a non-gasifiable impurity into a reaction zone, containing a molten metal bath, in a reactor maintained under conditions sufficient to dissociate the waste and to form a gasified feed component and a non-gasifiable impurity. The gasified feed component is then directed from the reactor to a regenerator furnace subsystem, maintained under conditions sufficient to convert the gasified feed component to the desired product.The apparatus of the invention includes a reactor having a waste inlet and a gaseous effluent, a reaction zone containing a molten-metal bath for dissociating the waste, containing a non-gasifiable impurity, and forming a gasified feed component, and a lance for injecting the waste into the reaction zone.

Abstract: A process for producing uranium hexafluoride comprises bringing fluorine gas into contact with reactive particles comprising uranium metal, as well as with non-reactive particles which are substantially inert and which are in contact with the reactive particles. The reactive particles are kept distinct from the non-reactive particles. The fluorine gas is allowed to react with the uranium metal at elevated temperature, thereby to produce gaseous uranium hexafluoride. The uranium hexafluoride is separated from any residual fluorine.

Abstract: A method for the production of low enriched uranium hexafluoride from highly enriched metallic uranium consists of oxidizing metallic uranium highly enriched in uranium-235 at a temperature of 700.degree.-1100.degree. C. and fluorinating with elementary fluorine at temperature of 300.degree.-1500.degree. C. with a fluorine excess exceeding the stoichiometric value, then sublimating and mixing in a gas flow the resultant highly enriched uranium hexafluoride with uranium hexafluoride containing uranium-235 within a range from 0.2 to 4.9% by weight, in a ratio defined by the equation: ##EQU1## where C.sup.HEU is the content of uranium-235 in the highly enriched uranium,C.sup.LEU is the content of uranium-235 in the low enriched uranium,C is the content of uranium-235 in uranium, the hexafluoride of which is used for mixing.

Abstract: Process for the treatment of a metal alloy based on uranium, generally in highly enriched form and other metallic elements, comprising a fluorination treatment with the aid of at least one fluorine-containing gas, optionally with an intermediate fluorination with the aid of a fluoric compound, a distillation treatment of the gaseous fluoride flow obtained in order to obtain pure uranium hexafluoride, as well as a mixing treatment of said hexafluoride with another more depleted hexafluoride to obtain the desired final isotopic content.

Abstract: A process for the selective electrofluorination of metallic alloy based on U characterized by effecting a selective anodic reaction on at least one of the components of the alloy by means of a controlled anodic voltage applied to the alloy in a bath of molten fluorides.

Abstract: A method of treating a gas based on fluorine and containing hydrofluoric acid, and which may optionally contain condensable gaseous compounds, especially uranium compounds, and non-condensable gases. The gas is refrigerated to obtain a gaseous component containing fluorine and any non-condensable gases present, and a liquid phase containing liquid HF and condensable compounds in solution and/or suspension. The liquid phase is filtered to recover the compounds in suspension.

Abstract: A multichamber type fluid bed reaction apparatus has a series of chambers formed by dividing the fluid bed part and the wind box part thereof with particular walls. Each reaction chamber is supplied with a reaction gas whose composition, flow amount and temperature can be selected arbitrarily. A fluid bed, a moving bed or a fixed bed may be used in each divided chamber. Regulation of particle formation, gas-particle reaction and amount of particles transferring between the chambers results in an improvement of efficiency and a simplification of the apparatus.

Abstract: A compound MF.sub.n, where M is a metal and n is the valency of the metal and has a value between 1 and 6, is subjected to a thermal plasma at a temperature in excess of 3000 K to dissociate it into the metal and fluorine. Also present in the reactor is an added reactant that will react with the metal or the fluorine to prevent their recombination so that there is formed fluorine gas or a fluoride other than the fluoride of the metal M.

Abstract: A method of fabricating uranium dioxide (UO.sub.2) powder from uranium hexafluoride (UF.sub.6) is disclosed, which comprises(1) reacting UF.sub.6 gas with steam with controlling the temperature of reaction between said UF.sub.6 gas and said steam at a predetermined temperature within the range of 200.degree. to 700.degree. C., to form solid uranyl fluoride (UO.sub.2 F.sub.2) and/or uranium oxide with an O/U ratio (oxygen-to-uranium atomic ratio) of 2.7 to 3,(2) dissolving said UO.sub.2 F.sub.2 and/or uranium oxide in water or nitric acid to form an aqueous uranyl solution containing UO.sub.2 F.sub.2 and/or uranyl nitrate (UO.sub.2 (NO.sub.3).sub.2),(3) reacting said aqueous uranyl solution with ammonia to precipitate ammonium diuranate (ADU),(4) filtering said precipitate,(5) drying said precipitate,(6) calcining said dry precipitate, and(7) reducing said calcined precipitate, whereby controlling the characteristics of said UO.sub.2 powder.

Abstract: The method for preparing a gaseous metallic floride is here disclosed which comprises reacting a metal or its oxide with a fluorine gas or nitrogen trifluoride gas, the aforesaid method being characterized by comprising the steps of mixing the metal or its oxide with a molding auxiliary comprising a solid metallic fluoride which does not react with fluorine and nitrogen trifluoride; molding the resulting mixture under pressure; and contacting the molded pieces with the fluorine gas or nitrogen trifluoride gas, while the molded pieces are heated.

Abstract: The process of the present invention provides a gas steam of a mixture of UF.sub.6 isotopes and an inert gas, e.g. nitrogen, which is adiabatically expanded through a nozzle into a laser light excitation zone and photodissociated to form U-235 enriched UF.sub.5.After the gas stream has passed through the laser light excitation zone, XeF.sub.6 is fed into the process gas stream so the the xenon hexafluoride remains protected against the dissociating radiation. The XeF.sub.6 may be mixed with the same inert gas that is employed for the adiabatic cooling of the UF.sub.6. The XeF.sub.6 reaction with U-235 enriched UF.sub.5 produces a stable complex of UXeF.sub.11, which polymerizes to poly(pentafluoroxenonium(+1)-hexafluorouranate V), an intermediate product of the present process. The intermediate product may be thermally decomposed to form U-235 enriched UF.sub.6 or U-235 enriched .beta.-UF.sub.5.

Abstract: A process of fabricating UO.sub.2 pellets comprising the steps of filtering and drying a slurry of ammonium diuranate (ADU) including ammonium fluoride (NH.sub.4 F), in order to form ADU powder, and then subjecting the ADU powder to calcining, reducing, compacting and sintering treatments, to form UO.sub.2 pellets.

Abstract: A method of controlling the crystal grain size of UO.sub.2 pellets is disclosed, which comprises(1) providing an aqueous uranyl solution which is free of hydrofluoric acid and nitric acid and which contains uranyl fluoride (UO.sub.2 F.sub.2) and/or uranyl nitrate (UO.sub.2 (NO.sub.3).sub.2) as a uranium component,(2) reacting with ammonia said aqueous uranyl solution to precipitate ammonium diuranate (ADU), while adjusting the ratio of said uranium components to a predetermined value within the range varying from the ratio 100% of uranyl fluoride and 0% of uranyl nitrate to the ratio 0% of uranyl fluoride and 100% of uranyl nitrate, adjusting the uranium concentration of the reaction mixture to 50 to 1,000 gU/liter and also adjusting the rate of contact between said uranium component in said aqueous uranyl solution with ammonia to at least 2 moles NH.sub.3 /min/mole U,(3) calcining and reducing said ADU precipitate to form UO.sub.2 powder, and(4) molding and sintering said UO.sub.2 powder, thus producing UO.

Abstract: A process for the preparation of uranium tetrafluoride by reduction of gaseous uranium hexafluoride using: (1) sulphur vapor with a minimum of halogen and/or a halide, chosen from among Cl.sub.2, Br.sub.2, S.sub.2 F.sub.2, SCL.sub.2, S.sub.2 Cl.sub.2, and S.sub.2 Br.sub.2 ; or (2) a minimum of one sulphur halide chosen from among S.sub.2 F.sub.2, SCL.sub.2, S.sub.2 CL.sub.2, and S.sub.2 Br.sub.2. The ratio R of the total number of gram-atoms of sulphur present during the reduction reaction to the number of gram-moles of UF.sub.6 is at least 0.6.

Abstract: The present invention contemplates the conversion of uranium hexafluoride with superheated steam to produce a fine, submicron, uranyl fluoride powder which is agglomerated and densified in a fluidized bed of a uranium oxide material. Thereafter, the agglomerated and densified uranyl fluoride is defluorinated and reduced in the fluidized bed to yield a fluoride containing uranium oxide material having a uranium to oxygen ratio of from about 1:2.0 to about 1:2.67. The so-produced fluoride contains uranium oxide material treated with steam and hydrogen to produce ceramic grade uranium dioxide.

Abstract: Method for fluorination of actinides and fluorides and oxyfluorides thereof using O.sub.2 F.sub.2 which generates actinide hexafluorides, and for removal of actinides and compounds thereof from surfaces upon which they appear as unwanted deposits. The fluorinating agent, O.sub.2 F.sub.2, has been observed to readily perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are thereby not destroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is easily prepared, stored and transferred to the desired place of reaction.

Abstract: A method for monitoring the stack gases of a purge cascade of a gaseous diffusion plant for uranium activity. A sample stream is taken from the stack gases and contacted with a volume of moisture-laden air for converting trace levels of uranium hexafluoride, if any, in the stack gases into particulate uranyl fluoride. A continuous strip of filter paper from a supply roll is passed through this sampling stream to intercept and gather any uranyl fluoride in the sampling stream. This filter paper is then passed by an alpha scintillation counting device where any radioactivity on the filter paper is sensed so as to provide a continuous monitoring of the gas stream for activity indicative of the uranium content in the stack gases.

Abstract: Method for recovery of actinides from nuclear waste material containing sintered and other oxides thereof using O.sub.2 F.sub.2 to generate the hexafluorides of the actinides present therein. The fluorinating agent, O.sub.2 F.sub.2, has been observed to perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are not destroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is readily prepared, stored and transferred to the place of reaction.

Abstract: Highly pure uranium hexafluoride is made from uranium oxide and fluorine. The uranium oxide, which includes UO.sub.3, UO.sub.2, U.sub.3 O.sub.8 and mixtures thereof, is introduced together with a small amount of a fluorine-reactive substance, selected from alkali chlorides, silicon dioxide, silicic acid, ferric oxide, and bromine, into a constant volume reaction zone. Sufficient fluorine is charged into the zone at a temperature below approximately 0.degree. C. to provide an initial pressure of at least approximately 600 lbs/sq. in. at the ambient atmospheric temperature. The temperature is then allowed to rise in the reaction zone until reaction occurs.

Abstract: An automated fuel rod production system includes a radioactive powder fabrication and processing stage, a pellet fabrication stage, a pellet processing stage, a tube preparation stage and a fuel rod fabrication and inspection stage, all of which provide a continuous (paced) mode of operation from the conversion of a radioactive gas to powder, through the fabrication of the powder into pellets, to completion of the assembly of the fuel rods. Extra capacity is designed into the system at critical points in the powder processing and pellet fabrication and processing stages to facilitate the continuous, paced mode of operation.

Abstract: A method of purifying a UF.sub.6 gas stream containing one or more metal fluoride impurities composed of a transuranic metal, transition metal or mixtures thereof, is carried out by contacting the gas stream with a bed of UF.sub.5 in a reaction vessel under conditions where at least one impurity reacts with the UF.sub.5 to form a nongaseous product and a treated gas stream, and removing the treated gas stream from contact with the bed. The nongaseous products are subsequently removed in a reaction with an active fluorine affording agent to form a gaseous impurity which is removed from the reaction vessel. The bed of UF.sub.5 is formed by the reduction of UF.sub.6 in the presence of UV light. One embodiment of the reaction vessel includes a plurality of UV light sources as tubes on which UF.sub.5 is formed.

Abstract: A process for the purification of uranium hexafluoride containing traces of neptunium fluoride and/or plutonium fluoride, wherein the uranium hexafluoride to be purified is contacted with a metal fluoride chosen from the group including lead fluoride PbF.sub.2, uranium fluorides of UF.sub.4+x in which x has a value between 0 and 1 and chromium trifluoride CrF.sub.3, at a temperature such that the plutonium and/or neptunium fluorides are reduced, and wherein the thus purified uranium hexafluoride is recovered.

Abstract: A physico-chemical cleaning process for the inner walls of a reactor which serves to maintain these walls in a state close to their main initial characteristics necessitated by a fluorination reaction, said characteristics being degraded by the deposition of a parasitic phase during the reaction, said initial characteristics being maintained by the use of a protective agent belonging to the group constituted by at least one of the reagents, a product resulting from the reaction, a product foreign to the reaction, but compatible with the substances of the main reaction or by the reaction of a third substance with at least one of the reaction substances or a mixture thereof, forming a renewable protective film on the said walls. The protective agent can be deposited by condensation on the walls before, during or after the main reaction, and then vaporized. The protective agent can be in liquid form, and trickling along the walls.

Abstract: A process for removing adhering or dust-like deposits in an apparatus which handles uranium hexafluoride. The process includes the steps of:(a) reacting the deposits with a gaseous boron halogenide other than boron trifluoride, to form at least one uranium halogenide; and(b) reacting the at least one uranium halogenide with a fluorine containing substance to form uranium hexafluoride.

Abstract: The invention relates to a process and apparatus for the separation of the isotopes of a body, and particularly of a heavy metal. The process comprises the preparation of a tension-active compound of said body, the solution of this compound in a liquid having a strong surface tension, the injection of a non-miscible body into this solution to form a plurality of separation surfaces, and the recovery of the fraction of the solution adjacent to said separation surfaces. The apparatus comprises a plurality of vats, means for injecting a gas into these vats to produce a foam, means to collect the foam and transfer it into a vat downstream, and means to transfer a portion of the liquid from one vat into another vat located upstream thereof. The process and apparatus are applied to the isotopic separation of uranium.

Abstract: A method is described for the preparation of high surface area metal fluorides and metal oxyfluorides comprising reacting high surface area metal oxides with a fluorocarbon vapor wherein the fluorocarbon is selected from the group consisting of CH.sub.4-Q F.sub.Q wherein Q is 1 to 3 and totally or partially fluorinated C.sub.2 -C.sub.6 alkanes, alkenes and alkynes and C.sub.5 -C.sub.6 cyclic alkanes, preferably fluoroform (CHF.sub.3) wherein the metal oxides and the fluorocarbon vapors are contacted at a temperature of from about 300.degree. to about 800.degree. C., for a time sufficient to effect the essentially complete conversion of the metal oxides into metal fluorides or the partial conversion of the metal oxides into metal oxyfluorides.

Abstract: A process for separating isotopes by selective excitation of isotopic species of a volatile compound by tuned laser light. A highly cooled gas of the volatile compound is produced in which the isotopic shift is sharpened and defined. Before substantial condensation occurs, the cooled gas is irradiated with laser light precisely tuned to a desired wavelength to selectively excite a particular isotopic species in the cooled gas. The laser light may impart sufficient energy to the excited species to cause it to undergo photochemical reaction or even to photoionize. Alternatively, a two-photon irradiation may be applied to the cooled gas to induce photochemical reaction or photoionization. The process is particularly applicable to the separation of isotopes of uranium and plutonium.

Abstract: This invention pertains to a method for removing deposits of uranium compounds in uranium hexafluoride handling equipment. A fluorocarbon containing bromine is internally injected into the handling equipment at or below ambient pressure and this brominating agent removes uranium compounds which have been formed therein. A fluoridating agent is also preferably used in conjunction with the fluorocarbon containing bromine.

Abstract: A method is described for the preparation of high surface area metal fluorides and metal oxyfluorides comprising reacting high surface area metal oxides with a fluorocarbon vapor wherein the fluorocarbon is selected from the group consisting of CH.sub.4-Q F.sub.Q wherein Q is 1 to 3 and totally or partially fluorinated C.sub.2 -C.sub.6 alkanes, alkenes and alkynes and C.sub.5 -C.sub.6 cyclic alkanes, preferably fluoroform (CHF.sub.3) wherein the metal oxides and the fluorocarbon vapors are contacted at a temperature of from about 300.degree. to about 800.degree. C., for a time sufficient to effect the essentially complete conversion of the metal oxides into metal fluorides or the partial conversion of the metal oxides into metal oxyfluorides.

Abstract: A process for making uranium metal from uranium oxide by first fluorinating uranium oxide to form uranium tetrafluoride and next electrolytically reducing the uranium tetrafluoride with a carbon anode to form uranium metal and CF.sub.4. The CF.sub.4 is reused in the fluorination reaction rather than being disposed of as a hazardous waste.