Thermal process for the conversion of uranium hexafluoride
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- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
- C01G43/025—Uranium dioxide
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B7/00—Halogens; Halogen acids
- C01B7/19—Fluorine; Hydrogen fluoride
- C01B7/191—Hydrogen fluoride
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2006/00—Physical properties of inorganic compounds
- C01P2006/80—Compositional purity
CA 022646l3 l998-ll-l3 W O 97/4S371 PCT~US96/19749 LH~M~r. PROCESS FOR THE CONVERSION
OF URANIUM HEXAFLUORIDE
- 5 Field of the Invention The present invention relates to a thermal process for the conversion of uranium hexafluoride (UF6) to give solid uranium oxide ~essentially UO2) and hydrogen fluoride (HF). The process represents an efficlent way of converting UF6 to UO2 with recovery of the attendant fluorine as HF by a single-step procedure involving two gaseous feed streams.
Related Application .5 This is a continuation-in-part of U.S. application Serial No. 08/635,190, filed April 19, 1996, the contents of which are incorporated herein ~y reference.
Backqround to the Invention The separation of uranium isotopes for defense needs and the preparation of commercial nuclear fuels have mainly been by processes that produce enriched and depleted uranium (i.e., enriched or depleted in the uranium-235 isotope) as UF6. Much of the enriched UF6 is converted to UO2 by processes selected to give the ceramic sinterability needed for preparation of nuclear fuel pellets. The much larger amounts of depleted UF6 from the enrichment process are mostly stored as solid UF6 in steel cylinders.
As of July, 1995, the U.S. Department of Energy had over 600,000 MT of depleted UF6 (containing over 400,000 - MT of uranium) stored in approximately 66,000 cylinders.
Long term strategies for management of this depleted uranium require conversion of the UF6 to uranium oxides.
However, while procedures for converting UF6 to uranium W O 97145371 PCTAUS96/19749 .
oxides are known, the currently available procedures are not particularly efficient or economical for converting depleted UF6 to solid uranium oxides, notably UO2, suitable for disposal, storage, or further use. More specifically, the UF6 conversions for nuclear fuels were developed to prepare UO2 with well controlled ceramic properties and are not optimum for the much larger-scale conversions of depleted uranium. Furthermore, because of the need to control their ceramic properties and the thermodynamic limitations, the known commercial conversion processes are complex with multiple process stages and include the formation of intermediate solids such as UO2F2 or UF4. Additionally, the fluorine by-products of these conversion processes are usually radioactive wastes with high disposal costs.
Uranium oxides are thermally and chemically stable, non-volatile and essentially insoluble in rain and ground water, and are the preferred compositions of uranium for long term storage or disposal. The most stable oxide in the environment is U30~, but other oxides ranging from UO2 to U409 and U03 and combinations of oxides are also acceptable products. Uranium and fluorine are very reactive elements chemically and, the conversion of UF6 to uranium oxides also produces a fluorine compound as a product. While some fluorine compounds have little commercial value and represent waste products with consequent disposal costs, hydrogen fluoride is a valuable commercial chemical with many uses to provide a market for the fluorine in the depleted UF6.
The conversion of UF6 into uranium oxides and HF
requires reaction with oxygen as ~2 or compounds containing oxygen and with hydrogen as H2 or compounds containing hydrogen. One process used to prepare nuclear W O 97/45371 PCTrUS96/19749 fuel UO2 from enriched UF6 uses gross excesses of water vapor and H2 in two steps with the two principal reactions belng:
UF6(g) + 2H2O(g) =~ UO2F2~s) + 4HF(g) (1 and UO2F2(s) + H2(g) =~ UO2(s) + 2HF(g) (2) where (g) and (s) represent, respectively, gas and solid.
The preferred sequence is to perform reaction (1) at about 250~C followed by reaction (2) at about 650~C.
The complete conversion of the uranium solids to UO2 as represented by reaction (2) requires good contact of the solids and gas over a relatively long period of time, .5 on the order of an hour or more. Other known conversion processes are precipitation of ammonium diuranate or ammonium uranyl carbonate from reaction of UF6 with aqueous solutions. All of these processes require multiple steps and give dilute aqueous fluoride solutions of little or no value as the fluoride product.
Nevertheless, these conversion reactions are chosen because they give the resulting uranium oxide the ceramic properties needed for fabrication of nuclear fuels.
Numerous U.S. patents have been issued directed towards processes for the conversion of UF6 to uranium oxides. See, for example, U.S. patent 4,830,841 and the U.S. patents listed therein which describe procedures for converting UF6 to uranium dioxide in furnaces, rotary kilns, fluidized beds or the like. As representative of such art, it is noted that U.S. patent 4,830,841 itself is concerned with a process for preparing UO2 from UF6 by reacting UF6 with steam to produce submicron uranyl fluoride powder, fluidizing a bed of uranium oxide W O 97/45371 PCTrUS96119749 material with a mixture of steam, hydrogen and inert gas at about 580~C to about 700OC, and introducing the submicron uranyl fluoride powder into the fluidized bed of uranium oxide material so that the uranyl fluoride powder is agglomerated, densified, fluidized, defluorinated and reduced to a fluoride-containing uranium oxide material which is removed from the fluidized bed and then contacted with hydrogen and steam at elevated temperature to obtain UO2 essentially free of fluoride.
Another U.S. patent 3,260,575 describes the preparation of ceramic UO2 fuel material by a single-step process comprising the reaction of UF6 with a stoichiometric excess, generally at least 1.5 times the stoichiometric amount, and preferably much larger (e.g., 30-40 times the stoichiometric amount) of a gaseous mixture of hydrogen and oxygen-bearing gas at a temperature above 1100~C and a pressure not exceeding 20 torr., i.e. 20 mm Hg absolute. The patent specifies that a temperature of at least 1100~C is required to avoid the formation of UF4 and that a pressure less than 20 torr is critical, fluoride intermediates being produced along with UO2 at higher pressures.
Another process directed towards the recovery of anhydrous hydrogen fluoride from UF6 gas is disclosed in U.S. patent 5,346,684 (equivalent to EP 529768 A1~. That process involves reacting UF6 in a primary reactor with steam to produce a uranyl fluoride intermediate and a gaseous mixture of hydrogen fluoride and water. The uranyl fluoride is then fed to a secondary reactor and reacted with water to produce a U3O8 product for disposal and a gaseous mixture of water, HF and oxygen. The gaseous mixtures from the two reactors are combined and W O 97/45371 PCT~US96/19749 then distilled to obtain an anhydrous HF product. An azeotrope of water and HF is vapori~ed and returned to the primary reactor.
Another prior process for converting UF6 to uranium - 5 oxides involves feeding the UF6 into a molten metal bath where the UF6 is bro~en down into recoverable components including uranium oxide and HF.
Notwithstanding the extensive prior efforts referred to above, there remains a substantial need for improved procedures for converting UF6, particularly depleted UF6, into solid UO2 in a form suitable for storage, disposal or use. The primary object of the invention is to provide such a process. Other objects, including, for example, the provision of HF in concentrated aqueous solution or i5 in other highly useful form, such as anhydrous HF, will also be evident from the description of the invention which follows.
SummarY of the Invention The invention provides a single-step process for efficiently converting UF6 into solid UO2 and gaseous or condensed phase HF. The process involves bringing together two gaseous reactant streams, one of the streams comprising UF6 optionally admixed with oxygen as ~21 and the second reactant stream comprising a mixture of hydrogen as H2 or as a hydrogen-containing compound and oxygen as an oxygen-containing compound, the gaseous reactant streams being brought together at a temperature, pressure and composition such that the UF6 is converted rapidly by flame reaction into readily separable solid uranium oxide (essentially UO2) and a gaseous H~ product.
While the composition of the two gaseous reactant streams can be varied, as discussed hereafter, care should be .
WO97/45371 PCT~S96119749 taken to avoid using mixtures which might create an explosive potential. For example, the second reactant stream preferably does not include the combination of H2 and ~2 because of the possibility of an explosion.
The present process is primarily intended for use with depleted UF6. However, the process can also be used with natural assay or enriched UF6. In either case, a solid oxide consisting essentially of UO2 and a gaseous HF
product are obtained. These are readily separated from each other with the gaseous HF product being condensed to provide a highly concentrated aqueous HF solution or anhydrous HF. This fluoride product can be used directly by the chemical industry for the manufacture of fluorine ~F2) or replacement refrigerants (e.g., non-chlorofluorocarbons) or by the uranium industry for the manufacture of UF4 and UF6. The solid UO2, which is readily collectable, is easily recovered for storage or use.
The process is not sensitive to the pressure of the reactants and the operating pressure of the system can be varied to accommodate sizing and throughput requirements.
However, it is particularly important to the usefulness of the process that the gaseous reactant streams are brought together and reacted at a pressure which is essentially atmospheric or above, although in some circumstances, it may be desirable to operate at a pressure slightly below atmospheric.
An important distinguishing feature of the present process over prior procedures is that it does not involve the use of fluidized beds, molten metal or the like to obtain the desired products. In essence, the present process simply involves bringing the two gaseous reactant streams together so that a flame reaction occurs and W O 97/45371 PCT~US96/~749 collects the resultant solid oxid'e product and gase~s HF
. , Description of Preferred Embodiments - 5 Preferably the feed stream comprising UF6 conta~ns at least part of the oxygen needed for the reaction, t~
balance, if any, of the oxygen being included in th~
second feed stream. The oxygen in the UF6 feed stre~lm should only be in the form of ~2 to avoid the pote~t~ial for premature reactions. It is also preferred that ~he UF6 feed stream does not contain H2.
The hydrogen in the second reactant stream can ~e in the form of H2 or as a hydrogen-containing compound ~ch as H2O, NH3 and/or CH4. Preferably all of the hydrog~n needed for the reaction is in the second feed strea,~.
Desirably, the second feed stream comprises a mixtu~ of H2 and H2O or a mixture of H2 and CO2.
While the composition of each gaseous reactant stream can be varied, care must be taken in preparin~
each stream to avoid the possibility of creating an explosion potential or premature reaction. For exa~le, undesirable mixtures include H2 and ~2~ UF6 and H2O, ~6 and H2, NH3 and ~2~ CH4 and ~2- Typical useful mixtures include, without limitation thereto, UF6 and ~2; (H2 and/or NH3) and H20, (NH3 and/or H2) and CO2; and CX4 ~nd H20 .
One or both feed streams may also include an irl~rt gas such as argon or nitrogen.
The reaction can be carried out over a relativ~ly wide temperature range such as between 900~C to 15~Q~C or higher, e.g. up to 2000~C, with a temperature of around 1100~C being generally preferred. The reaction temperature or, stated otherwise, the temperature ~f the . ,~ ~, . .,, . . _ CA 02264613 1998-ll-13 W O 97/45371 PCTrUS96/19749 reaction product, can be controlled by varying the amount of oxygen in the UF6 feed stream and the flow rate of the gases used for the reaction.
The reaction can be carried out over a relatively broad pressure range such as between atmospheric and 250 psia. It may be useful in some cases to operate at slightly below atmospheric, e.g. at about to to 13 psia, and possibly as low as 5 psia, but atmospheric or essentially atmospheric pressure is preferred. If a temperature in excess of 2000~C is used, the pressure is preferably decreased below atmospheric to minimize the formation of undesired by-products (e.g. UF4).
The ratio of hydrogen and oxygen to UF6 can also be varied to control the amount of water vapor in the gaseous HF product. However, generally speaking, the amounts of oxygen and hydrogen in the feed gases, i.e., the total amount of oxygen and hydrogen used in the process, should be less than about 1.5 times the stoichiometric amounts needed for reaction with the UF6 to form UO2 and HF. Preferably the hydrogen and oxygen are used near (i.e., around 10-30~ in excess of) the stoichiometric amounts.
A particularly unique feature of the invention is the finding that the desired reaction to provide UO2 and HF can be accomplished in a very short period of time.
Typical reaction times are on the order of fractions of a second although times in excess of this can be used.
Advantageously the process is carried out using a closed crucible or reactor made of suitable refractory material, e.g. graphite or alumina. High melting point nickel and nickel alloys that form stable metal fluorides can also be used. The gaseous reactant streams are fed separately to the reactor. Within the specified CA 02264613 1998-ll-13 W O 97/45371 PCTrUS96/19749 temperature range of the invention, the reactant streams react essentially spontaneously on contact within the reactor to provide solid UO2 and gaseous HF. The UO2 can be collected from the bottom of the reactor or filtered from the reactor off-gas while the HF may be withdrawn from multiple points, e.g. reactor top or side, and, if desired, condensed.
Advantageously, the reactant streams are fed into the reactor to obtain intimate mixing of the reactants such as through a concentric tube arrangement, with the UF6 gas being fed through, for example, the inner tube and the other gaseous reactant stream being fed through an outer tube. The desired reaction occurs at the exit or discharge ends of the concentric tubes where the reactant streams come together. Alternatively, the gaseous reactant streams can be fed to separate inlets of a nozzle arrangement rather than using concentric tubes, the reactant streams being brought together at or just before the nozzle discharge. In either case, one or both of the reactant streams can be preheated, for example, to 700-1000~C. The reaction does not require the application of additional heat as the overall reaction is an exothermic one. With appropriate selection of the composition of the reactant gas streams, an equilibrium reaction temperature of around 900-2000~C is readily attained. Preheating of the reactant gas streams is generally desirable, particularly if oxygen is not included in the UF6 reactant gas.
A suitable way of practicing the invention comprises the use of a burner designed to receive UF6 in one feed stream which may also contain ~2 and another separate feed stream comprising H20 or CO2 which also contains the principal source of hydrogen as H2, NH3 or CH4. The ~2 and W O 97/45371 PCTAJSg6/19749 H2O and/or other oxygen-containing compounds together should preferably supply a slight excess, e.g. 10 to 20 percent over the stoichiometric amount, of oxygen over that needed to form UO2. The H2O and/or other hydrogen-containing compounds together should also supply a slight excess of hydrogen over that needed to form HF. The excess of oxygen forms C0 if carbon is present and HzO if excess hydrogen is present. While a stoichiometric excess of hydrogen and/or oxygen is generally preferred, it is recognized that sub-stoichiometric amounts of hydrogen and/or oxygen can also be used to provide a somewhat different uranium oxide product distributio~.
As noted earlier, the oxygen feed rate (when ~2 iS
admixed with UF6) is used to control the temperature ~
the products of reaction. Without oxygen feed, the ~ases should preferably be preheated to control the tempera~ure of the products of reaction in the desired range specified for the present process, i.e. 900-2000~C or higher.
Brief Descri~tion of the Drawings The invention is further described by reference t.o the accompanying drawings wherein:
Fig. 1 is a flow diagram showing one arrangement for practicing the present process;
Fig. 2 graphically shows equilibrium compositioi~s versus product temperature using a reaction arrangeme~t as in Fig. 1;
Fig. 3 diagrammatically shows in more detail one. way of supplying the reactant gas streams to the reaction zone;
Fig. 4 shows an alternative flow diagram for th~e~
practice of the invention; and W O 97/45371 PCTrUS96/19749 Fig. 5 diagrammatically illustrates another arrangement for bringing the reactant streams together ~ for reaction.
With more specific reference to Fig. 1, two gaseous - 5 reactant streams (1) and (2) are fed continuously to a lance or burner (3) comprising a pair of concentric tubes (4) and (5) positioned within the reaction vessel (6).
A pre-heated gaseous mixture of UF6 and ~2~
optionally including an inert gas such as N2 or argon, is fed through the inner tube (4) while a pre-heated gaseous mixture of H2, NH3 and/or CH4 and H2O or CO2, optionally with inert gas such as N2 or argon, is fed through the outer tube (5). Optionally, gaseous feeds are heated in the lance or burner (3) by an external heating source on vessel (6). The two gaseous streams mix and essentially simultaneously react at the discharge ends of the tubes to form UO2 and HF without any significant accumulation of intermediate uranium compounds as solids. The reaction products discharge into the lower portion of vessel (6) which is preferably provided with means to facilitate separate discharge of gases and solids. The uranium oxides are recovered at (7) as dry, granular solids suitable for known methods of storage, disposal or use.
The gaseous products collected at (8) are filtered (not shown) to remove entrained solids and cooled in condenser (9) to allow separation of condensed HF and residual H2O
(10). By appropriate selection of the composition of the reactant streams, the amount of water formed in the reaction can be controlled to provide the desired concentration of HF solution resulting from the condensation at (10). The resulting condensed product has many commercial uses as collected in the form of highly concentrated aqueous HF or essentially anhydrous , CA 02264613 1998-ll-13 W O97/45371 PCTrUS96/19749 HF. The non-condensable gases (11) may be partly recycled to feed (1) or (2) or they may be totally discharged from the system for use or disposal.
Figure 2 is discussed hereafter in connection with Example 2. The figure, as earlier noted, shows that the optimum results, with respect to the production of UO2 and HF at atmospheric pressure, are realized at an equilibrium temperature in the range of 900~C to 2000~C, particularly around 1100~C.
Figure 3 shows a feed apparatus for introducing a pre-heated feed gas containing UF6 and a second pre-heated feed gas containing compounds of hydrogen and oxygen.
The UF6 feed (12) flows through an inner tube (14) selected to be corrosion resistant for UF6 and ~2 and for all the other gaseous feeds. The other gaseous feed mixture ~13) flows through the annulus between the inner tube and a second, larger tube (15) selected to be corrosion resistant for HF and for the gaseous feed mixtures. Al2O3, nickel, and nickel alloy tubes can be used when they are passivated by a film of solid fluorides. Alternatively, other fluoride compatible materials, such as CaF2 and lanthanum hexaboride, may also be used.
A third, large, graphite tube (not shown) can be placed around the tube (15) so as to provide for an inert gas flow to prevent excessive temperatures and, more importantly, avoid corrosion of the outer surface of tube (15). The UF6 feed ~12) includes a controlled supply of ~2 to regulate the reaction temperature and, optionally, N2, argon or other inert gas. The feed (13), as shown, comprises H2, NH3 or CH4 and H2O or CO2 as the hydrogen and oxygen sources. Optionally, N2, argon or other inert gas may also be included in feed (13). As in the case of the CA 022646l3 l998-ll-l3 W O 97/45371 PCTrUS96/1~49 system shown in Figure 1, the pre-heated gases issu.i~g at the exits of tubes (14) and (15) flame react essentially simultaneously as they come in contact (see "Reactio~
Zone") to form the desired solid U02 and gaseous HF ~hile leaving H20 and H2 as excess reactants and inerts (Arr N2) in the embodiment as shown.
Figure 4 shows an arrangement which is useful ~
avoid excessive temperatures or larger heat fluxes. In this embodiment, the pre-heated oxidizing feed gas containing UF6, O2 and N2 or argon and the pre-heated reducing feed gas (17) comprising a mixture of H2, N~.~ or CH4; H20 or C02; and N2 or argon, flow through a lanc~ ~r burner (18) to mix and react at the-lance or burner tip 18a inside reactor vessel (20). Part or all of the s,~lid uranium oxide product accumulates at (23) for perio~c discharge from the reactor vessel t20). Gaseous products and any entrained uranium oxide solids exit continu.~sly at (22) into a suitable separating system (not shown).
The reactor temperature may be controlled by a combination of means for heating or cooling the rea~or by jacket (21), control of the amount cf ~2 in the feed stream (16), and pre-heat of the feed streams (16) a~d (17). Preheating the reactor by operation of the r~ctor as a burner without UF6 and use of an ignition devic~ (19) may also be employed as desired or if necessary to initiate the process. Generally speaking, the temperature and composition of the feed streams are ~uch that when the two streams are brought together, a f:~ame reaction occurs. If desired, however, the igniter (l9) may be positioned at the point where the gaseous st.reams come in contact to assist in the initiation of the reaction, although this is not usually necessary, particularly if the gaseous streams have been preheated.
.. . ..
CA 02264613 1998-ll-13 W O 97/45371 PCTrUS96/19749 Figure 5 shows an alternative to the concentric tube arrangement of Figure 3. Thus, in Figure 5, the reactant streams (24) and (25) are separately supplied through inlets (26) in nozzle means (28), the gases coming into contact adjacent the nozzle discharge where they react to form UO2 and HF as in the Figure 3 arrangement.
The invention is illustrated by the following examples:
Example 1 An experiment was done with gas feeds to a feed apparatus generally as described in Fig. l except that the feed arrangement into the reactor comprised three concentric tubes rather than two as shown. A mixture of lS UF6 at a rate of 250 g/hour and Ar was fed to an inner Al2O3 tube. A mixture of water vapor at about 31 g/hour, H2 at 19 std liters/hour and Ar was fed into the annulus between the inner tube and a middle Al2O3 tube. Ar was fed into the annulus between the middle tube and an outer graphite tube. The assembly of tubes discharged into the reactor chamber at about 950~C. The uranium collected as solids beyond the tip of the inner tube with an estimated 0.1 second residence time between the end of the inner tube and the point of deposition of the uranium product. Analyses of the deposited solids by X-ray diffraction showed essentially pure UO2 without detectable amounts of fluoride compounds.
Exam~le 2 Thermochemical calculations were made using a computer program [HSC Chemistry for Windows 1.2, Outokumpu Research OY, FORI, Finland] to determine the equilibrium compositions of products and the adiabatic CA 022646l3 l998-ll-l3 W O 97/45371 PCTrUS96/19749 temperature for reaction without heat transfer. The equilibrium compositions versus temperature at essen-tially atmospheric pressure (l.o Bar) are shown in Figure 2 for reaction of 1.0 mole of UF6, 0.5 moles ~f ~2~ 1 . 4 moles of H2O, 2.2. moles of H2 and 2 moles of Ar at atmospheric pressure. The equilibrium composition at 1100~C is more than 99~ conversion of the UF6 to UO2 and HF. With the feed gases pre-heated to 100~C, the product temperature would be 1108~C. The same equilibrium composition shown in Figure 2 would also result if the same total molar amounts of hydrogen and oxygen were fed using other combinations of H2, H2O and ~2- However, the adiabatic temperatures would be less than 500~C for no ~2 (i.e., all the oxygen as H20) and over 2000~C for no H2O
(i.e., all the oxygen as ~2) . This illustrates how the composition of the products and the temperature without heat flux can be controlled separately.
An important feature of the invention is that the UF6 conversion reaction is completed quickly within a very short time and distance after the pre-heated UF6 gas stream is mixed with the other reactant gas stream, e.g.
a gas stream comprising H2O and H2, possibly with an inert gas such as argon. Typically, the residence or reaction time is in the order of fractions of seconds, for example, 0.1 second using a total gas velocity at the tip of the feed lance or burner of about 3.5 feet per second.
Without intending to be limited to any particular theory of operation, the invention appears to be based on a number of important factors. These include the finding that, using particular reaction conditions and procedures, uranium oxide solids can be produced from a very rapid, one-step process for conversion of UF6.
Another important finding is that, by using the , .. . . . . . .
CA 02264613 1998-ll-13 W O 97/45371 PCTrUS96/19749 conditions described herein, and the indicated feed configurations, for example, one pre-heated gaseous stream comprising a mixture of H20 and H2 and another pre-heated feed stream of UF6, with or without oxygen and inert gas, conversion of UF6 to essentially UO2 solids can be obtained without significant accumulation of UF4, UO2F2, or other uranium fluoride solids as intermediate compounds. Another important finding is that the adiabatic product temperature can be controlled by controlling the temperatures and compositions of the feeds.
It is known that UF6 gas can be reacted with either H2 or H2O gas to give useful conversions as follows:
UF6(g) + H2(g) -> 2HF(g) + UF4(s) (1) UF6(g) + 2H20(g) -~ 4HF(g) + U02F2(s) (2) The first reaction is used as the initial step for - preparation of enriched uranium metal from enriched UF6.
The UO2F2 from reaction (2) is not directly a useful product but can be an intermediate for conversion to commercial nuclear fuels by reaction (3):
U02F2(s) + H2(g) -~ 2HF(g) + UO2(s) (3) This conversion reaction of a solid with a gas is more difficult than reactions ~1) or (2) where only gaseous reactants are involved. Reaction (3) commonly requires long times with good mixing of solids with an excess of H2. Reaction (1) might be used in combination with reaction (4) to prepare UO2 from UF6:
UF4(s) + 2H20(g) -> 4HF(g) + UO2(s) (4) Reaction (4) is much less practical than reaction (3) because it is less favorable thermodynamically and the UF4 from reaction (1) is a fused solid of low surface area.
According to the present invention, the reaction of an H2/H2O gas mixture with UF6 gas at the specified conditions and feed compositions results in conversion of the UF6 in a single process step to essentially uranium oxide UO2 without formation of significant amounts of intermediate uranium compounds. The overall converslon may be represented by reaction (5):
UF6(g) + 2H20(g) + H2(g) -> 6HF(g) + UO2(s) (5) While reactions (1) or (2) (or other reactions) might occur on a molecular scale, the mixing of gases H2/H20 and UF6, or modifications thereof according to the invention, apparently allows reactions (3) or (4) to complete the conversion to uranium oxides while the intermediate products are still in a very finely divided (nearly molecular) state.
Thermochemical calculations can be used to identify the limiting requirements for the foregoing reactions.
The equilibrium compositions were calculated for each uranium reactant and a ten percent excess of the other reactants. The results are given below as percentage conversions of the uranium feed over the most favorable range of temperature at atmospheric pressure. The adiabatic product temperatures for these feeds pre-heated at 700~C were calculated as an indication of the heating or cooling requirements.
CA 022646l3 l998-ll-l3 W O 971~5371 PCTrUS96/19749 Resulting Adlab~ti c Reaction No. Equilibrium Converslon Product Temp. ~C
(for products in the indicated for feeds at temperature range) 700~C) 1 ~100~ for 0 to 2500~C 1885 2 ~99~ for 0 to 750~C 1058 3 ~98~ ~or 850 to 1300~C 639 4 ,98~ for 850 to 1400~C -273 ,99% for 900 to 1300~C 1000 These thermochemical calculation results show that the reaction of UF6(g) with a mixture of H2(g) and H2O(g) (reaction (5)) provides a well-controlled conversion with a good yield of UO2 and HF. The equilibrium conversions for reaction (5) are good over a 900 to 2000~C range of temperatures. Reactants preheated to a reasonable temperature (700~C) give products within this temperature range without reactor heat transfer for control.
Additional excesses of H2 or H2O feeds can be favorable to more complete conversions. The two products are solid (UO2) and gaseous (HF) over wide temperature ranges, thus allowing simple physical separation of the products.
The four reactions (1) to (4) are much less favorable in one or more respects than reaction (5).
Reaction (1) is very exothermic and will typically give UF4 as a vapor or liquid requiring cooling to prepare the UF4(s) for subsequent reaction to UO2 by reaction (4) in a second reactor. Reaction (4) is extremely endothermic and will require large heat inputs to hold the favorable range of temperatures. Reactions (2) and (3) are mildlv exothermic and endothermic, respectively. But reactio (2) requires limiting the temperature to avoid thermal decomposition of the UO2F2 product. Reaction (3) must be SUBSTITUTE SHEET (RULE 26 W O 97/45371 PCTrUS9C/19749 carried out with a large excess of H2 to complete the reaction without thermal decomposition of the UO2F2 feed.
Only reaction (5) can be carried out to give a solid product and high conversions without large heat fluxes or large excesses of H2O or H2 feeds.
For the conversion of UF6 by reaction (5), all the oxygen may be supplied as H2O(g). Thermochemical calculations indicate that the feeds are preferably preheated to 700~C so the products can be at an optimum temperature for complete conversion without requiring heat transfer from the reaction zone. The same conversion products could be formed with oxygen supplied by ~2 (g) as shown by reaction (6):
UF6(g) + O2(g) + 3H2(g) ~ 6HF(g) + UO2(s) (6) Reaction (6) is very exothermic and feeds at 25~C
result in adiabatic product temperatures over 2000OC.
This high temperature is undesirable from a practical viewpoint and is less favorable thermodynamically primarily because UF4(g) becomes a significant product.
The most practical conversion of UF6(g) to uranium oxides and HF involves supplying oxygen as both ~2 (g) and H2O(g) with the proportions controlled to control the product temperature. The reaction for half of the oxygen from H2O(g) and half from ~2 (g) is:
UF6(g) + 0.5O2(g) + H2o(g) + 2H2(g) ~ 6HF(g) + UO2(s) (7) Since large heat fluxes are not needed and temperatures are limited, the design of the equipment is simplified and a relatively wide variety of materials of construction are acceptable for use. Thus, while ceramic CA 022646l3 l998-ll-l3 W O 97/45371 PCT~US96/19749 materials such as alumina or graphite are generally preferred, the invention permits operations wherein the reactor wall may be substantially cooler than the reaction temperature, thus allowing the use of metals such as nickel or Monel. Resistance heating elements on the reactor wall may also be adequate. Alternatively, an induction heating system may be used to heat the reactor.
Adiabatic product temperatures were calculated using ten percent excesses of both oxygen and hydrogen with feeds at 25~C and the division of oxygen supplied between O2(g) and H2O(g) as a variable. The results are:
Adiabatic Product Temperature for products UF6 02 H2O H2 ~f 6HF(g)+UO2+0 2H2O(g) Moles Moles Moles Moles +O.lH2(g) 1 0 2.2 1.1 370~C
1 0.15 1.9 1.4 637~C
1 o. 30 1.6 1.7 891~C
1 0.45 1.3 2.0 1146~C
1 0.60 1.0 2.3 1389~C
1 0.75 0.7 2.6 1631~C
1 1.10 0 3.3 2143~C
The 1146~C for UF6:O2:H2O molar ratio of 1:0.45:1.3 appears to be near the middle of the optimum temperature range. The amount of O2 may be controlled from a temperature measurement. Less ~2 iS needed if the feeds are preheated above 25~C.
Only two gaseous feed streams are needed since H2O
and H2 do not react with each other and UF6 and O2 do not react below 1000~C. A large excess of H2 (e.g. greater than 50~ theoretical) may be acceptable as the excess can be recycled after condensation of the HF product. The SUBSTITUTE SHEET (RULE 26 W O 97/45371 PCTrUS96/19749 excess of ~2 should be well-controlled and small (up to, for example, 20~ excess), particularly if an anhydrous HF
product is desired to minimize the amount of water in the H~.
As will be evident from the foregoing, the process of the invention comprises reaction of two gaseous feed mixtures to give a one-step, efficient conversion of UF6 into uranium oxide and HF. The gaseous feed compositions and temperatures are controlled to give the optimum compositions of uranium oxide and of gaseous products for recovery of condensed HF as a chemical of significant commercial value. In a preferred embodiment, one gaseous feed comprises UF6, e.g. depleted UF6, together with inert gas and/or part of the oxygen needed for the conversion.
The other gaseous feed comprises hydrogen as H~, H~O, NH3 or CH4 and all or part of the required oxygen as H2O or CO2. Increasing the fraction of oxygen supplied as ~2 will generally increase the reaction temperature or the temperature of the products after reaction. On the other hand, increasing the fraction of oxygen supplied as H2O or CO2 will generally decrease the temperature of the product after reaction. The gaseous feeds may also be preheated before mixing to increase the temperature of the products after reaction. This control of temperature is important to simplify the design of process equipment. Avoiding excessive temperatures allows the use of nickel or other metals instead of ceramics. The control of temperatures without need for large heat fluxes at the reaction zone is also an important advantage or simplification.
Specific features of the invention include the following:
.. . .
W O 97/45371 PCTrUS96/19749 ~1) The process provides uranium oxides from UF6 which have useful properties sufficient to meet the requirements for storage, disposal or use of uranium.
(2) The process provides a one-step conversion of UF6 into uranium oxide and HF. The UF6 starting material and the other reactants are fed into a reaction zone to give readily separable solid and gaseous products.
(3) The process involves the feed of two or more gaseous feeds which are separately stable with compositions and temperatures that give a favorable ~hermodynamic equilibrium composition and temperature with little or no heat transfer during the reaction. One gaseous feed is the UF6 with varying amounts of ~2 and/or inert diluent gas, such as Ar. The other gaseous feed includes one or more sources of hydrogen (H2, NH3, H2O or CH4) and one or more sources of oxygen (H2O, CO2). The composition of each gaseous feed stream, the ratios of the two feed streams, and the temperatures of the feeds can be controlled and varied to provide the favorable thermodynamic e~uilibrium compositions and temperatures.
(4) The preferred reaction product temperatures for conversion of UF6 into uranium oxides and HF are most commonly in the range of 900~ to 2000~C.
(5) The preferred reaction pressure for conversion of UF6 into uranium oxide and HF is commonly in the range of atmospheric, but elevated pressures can be accommodated.
(6) The process results in a gaseous product composition that can be controlled to allow recovery of HF for commercial use.
(7) The reaction temperature may be controlled by controlling the fractions of oxygen fed as ~2 and fed as H2O or CO2. Increasing the fraction added as ~2 increases CA 02264613 1998-ll-13 W O 97/45371 PCTrUS96/19749 the temperature of the reaction products; increasing the fraction fed as H2O or C02 decreases the temperature.
This control of temperature prevents excessive temperatures, minimizes or eliminates the need for heat transfer to and from the reactlon zone and provides an optimum temperature for obtaining the compositions of products desired.
(8) The product compositions can be controlled and varied by varying the proportions of total oxygen to UF6 and total hydrogen to UF6 in the feeds. Since the oxygen in the feed can be from ~2 and H2O or C02 and the hydrogen can be from H2 and H2O, the control of oxygen/UF6 and hydrogen/UF6 ratios can be independent of the control of reaction temperature as described in (7).
(9) Control of temperature can also be accomplished by a controlled preheating of the gaseous feeds. For example, feeds of UF6 (without ~2) and H2 + H20 can be preheated to about 700~C to give an adiabatic reaction temperature within the preferred range of temperatures.
(10) The feed apparatus and procedures allow the gaseous feeds to be fed and reacted directly to final product without excessive corrosion or erosion by the feeds and without handling and plugging problems caused by bulk solids of uranium intermediates such as U02F2 and UF4. The conversion of UF6 to uranium oxides is completed without need for a mixing of a gaseous feed with uranium solids of an intermediate composition (e.g. U02F2 or UF4).
The mixing and reaction of a gas with bulk solids is commonly slower and more difficult than the mixing and reaction of gases. The elimination of such a process operation is a major difference between the present invention and prior art procedures.
.. , .. . ~ ~ . . ..
W O 97/45371 PCTrUS96/19749 (11) The two principal products in the present process are a solid (uranium oxide, primarily as UO2) of very low volatility and gaseous HF which can be condensed when cooled. This allows easy and efficient separation of the uranium oxide product and the HF product by simple physical separation (e.g., filtration).
(12) The control of reaction temperatures and heat fluxes by controlling feed composition (more specifically, the oxygen content of the UF6 feed) greatly simplifies the design of the process equipment. Some materials of construction and temperature control procedures are more practlcal for the process described than for highly exothermic or highly endothermic process reactions. Mildly exothermic process reactions might be contained by cooled metal reactor walls without the need for ceramics. Low heat fluxes through the reactor walls allow simpler heat transfer and temperature control designs.
(13) The process may be carried out continuously under substantially adiabatic conditions with the oxide solids and gaseous HF periodically or continuously removed from the reactor.
It will be appreciated that various modifications may be made in the invention as described above without deviating from the spirit and scope thereof as defined in the following claims wherein:
Priority Applications (3)
|Application Number||Priority Date||Filing Date||Title|
|US08657937 US5752158A (en)||1996-04-19||1996-05-30||Thermal process for the conversion of uranium hexafluoride|
|PCT/US1996/019749 WO1997045371A1 (en)||1996-05-30||1996-12-19||Thermal process for the conversion of uranium hexafluoride|
|Publication Number||Publication Date|
|CA2264613A1 true true CA2264613A1 (en)||1997-12-04|
Family Applications (1)
|Application Number||Title||Priority Date||Filing Date|
|CA 2264613 Abandoned CA2264613A1 (en)||1996-04-19||1996-12-19||Thermal process for the conversion of uranium hexafluoride|
Country Status (4)
|US (1)||US5752158A (en)|
|CA (1)||CA2264613A1 (en)|
|EP (1)||EP0906245A4 (en)|
|WO (1)||WO1997045371A1 (en)|
Families Citing this family (11)
|Publication number||Priority date||Publication date||Assignee||Title|
|US5935528A (en) *||1997-01-14||1999-08-10||Molten Metal Technology, Inc.||Multicomponent fluid feed apparatus with preheater and mixer for a high temperature chemical reactor|
|US5875385A (en) *||1997-01-15||1999-02-23||Molten Metal Technology, Inc.||Method for the control of the composition and physical properties of solid uranium oxides|
|FR2771725B1 (en) *||1997-11-28||2000-02-04||Franco Belge Combustibles||Method and direct conversion of uranium hexafluoride to uranium oxide device|
|FR2788760B1 (en) *||1999-01-27||2001-03-23||Cogema||heat transfer system for reactor conversion of UF6 into uranium oxide|
|GB0427968D0 (en) *||2004-12-21||2005-01-26||Davy Process Technology Switze||Process|
|EP1985587A1 (en)||2007-04-27||2008-10-29||Westinghouse Electric Company LLC||Two step dry UO2 production process|
|EP2277831B1 (en)||2009-07-20||2012-05-23||Westinghouse Electric Company LLC||Two step dry UO2 production process utilizing a positive sealing valve means between steps|
|US7824640B1 (en)||2006-07-25||2010-11-02||Westinghouse Electric Co. Llc||Two step dry UO2 production process utilizing a positive sealing valve means between steps|
|US20080025894A1 (en) *||2006-07-25||2008-01-31||Lahoda Edward J||Two step uo2 production process|
|CA2815580A1 (en)||2010-11-08||2012-05-18||Colibri Technologies Inc.||Systems and methods for improved visualization during minimally invasive procedures|
|FR3006308A1 (en) *||2013-05-31||2014-12-05||Commissariat Energie Atomique||Process for the production of uranium dioxide and hydrofluoric acid.|
Family Cites Families (10)
|Publication number||Priority date||Publication date||Assignee||Title|
|US3260575A (en) *||1964-11-19||1966-07-12||Richard L Heestand||Single-step process for preparation of uranium dioxide from uranium hexafluoride|
|GB1426159A (en) *||1973-08-10||1976-02-25||Gen Electric||Process for producing uranium dioxide rich compositions from uranium hexafluoride|
|US3970581A (en) *||1975-05-12||1976-07-20||General Electric Company||Multiple gas streams in the post oxidation step in a process for converting uranium hexafluoride to uranium oxide rich compositions|
|US4003980A (en) *||1975-05-21||1977-01-18||Exxon Nuclear Company, Inc.||Uranium dioxide preparation|
|US4005042A (en) *||1975-07-02||1977-01-25||General Electric Company||Process for producing uranium rich compositions from uranium hexafluoride using fluid injection in the post oxidation step|
|US4031029A (en) *||1975-07-02||1977-06-21||General Electric Company||Process for producing uranium oxide rich compositions from uranium hexafluoride using fluid injection into the reaction zone|
|US4830841A (en) *||1984-12-24||1989-05-16||Advanced Nuclear Fuels Corporation||Conversion of uranium hexafluoride to uranium dioxide|
|JPH0313172B2 (en) *||1985-06-04||1991-02-21||Mitsubishi Materiaru Kk|
|US4698214A (en) *||1985-08-12||1987-10-06||General Electric Company||Method and combustion reactor for converting uranium hexafluoride gas to an oxide of uranium|
|CA2068068A1 (en) *||1991-08-30||1993-03-01||James H. Mestepey||Recovery of anhydrous hydrogen fluoride from depleted uranium|
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