US3243256A - Processes for the dissolution of uranium in nitric acid - Google Patents

Processes for the dissolution of uranium in nitric acid Download PDF

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Publication number
US3243256A
US3243256A US28547763A US3243256A US 3243256 A US3243256 A US 3243256A US 28547763 A US28547763 A US 28547763A US 3243256 A US3243256 A US 3243256A
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United States
Prior art keywords
uranium
solution
dissolution
nitric acid
velocity
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Expired - Lifetime
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English (en)
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Rateau Arthur
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Definitions

  • the present invention relates to an improvement in processes for the dissolution of uranium in nitric acid.
  • a process for the dissolution of uranium is already known, which consists in operating in a discontinuous manner by placing metallic uranium, in the form of rods for example, in a receptacle containing nitric acid maintained at the boiling point and in effecting complete dissolution of the metal under these conditions.
  • the disadvantage of such process is that, for the same velocity of penetration of the :acid into the metal, overall velocity of dissolution, in proportion to the metal surface exposed to the acid, decreases progressively as the surface decreases. In consequence, the velocity becomes very low at the end of the attack on the metal by the acid, which involves undesirable imm-obilisation of the material.
  • a so-called continuous process is also known, which consists in supplying both fresh acid and metal to the receptacle in a regular manner, in order to obtain a substantially constant velocity of dissolution.
  • the reaction can be favoured by increasing the temperature, but this expedient is limited by the complication which is necessarily involved in maintaining a suitable pressure, for example equal to the atmospheric pressure, inside the receptacle.
  • a suitable pressure for example equal to the atmospheric pressure, inside the receptacle.
  • the present invention relates to a process which allows a velocity of attack by nitric acid to be attained with uranium which is at least as high as that which is obtained ordinarily with uranium/molybdenum alloys.
  • This process consists in attacking metallic uranium with a nitric solution containing a quantity of uranium previously dissolved in state of uranyl nitrate, the concentration of uranyl ions in the solution being maintained at a constant elevated value.
  • FIG. 1 shows a set of graphs plotted on a coordinate system having, as .abscissae, the free acidity of the attacking solution and, as ordinates, the velocity of dissolution, thus showing the effect of the concentration of uranyl ions in the solution;
  • FIG. 2 is a diagram illustrating one embodiment of a dissolver which operates according to the process of the invention.
  • the process relates particularly to an operation carried out continuously by using predetermined quantities and proportions of an attacking liquor constituted by nitric acid and uranyl nitrate.
  • the velocity of attack that is to say, the weight of uranium dissolved with respect to the reactable surface presented by the metal
  • the concentration of the liquor in uranyl ions is large, as is also shown by the following table in which the velocity of attack of the uranium is given in mg. per sq. cm. and per minute, using an acid containing 4.5 moles of free HNO per litre, as a function of the quantity of uranyl nitrate present in the solution.
  • the process can be carried out as a continuous operation in a dissolver which itself is of the standard type.
  • This apparatus of stainless steel, comprises a dissolution tank 1 of generally cylindrical form connected by a flange joint 2 to a column 3.
  • the lower part 6 of the dissolution tank l is provided with a perforated plate, at the level indicated at 4-, serving to support uranium rods to be dissolved, and is surrounded by a lateral jacket 5 provided with a standard heating system.
  • the column 3 is connected at its other extremity to an assembly comprising a condenser and an absorber.
  • the condenser is intended to cool the vapours produced during the dissolution of the uranium by the acid inside the dissolver and to condense the water vapour.
  • the absorber serves to recombine the nitrous vapours in order to reintroduce them for a further cycle through the dissolver tank.
  • the condenser 7 is connected at one end to the pipe forming the column 3 and includes an inlet 9 for the admission of oxygen to the inside of the condenser, in order to oxidise the vapours circulating in the pipe 3 to elTect their recombination as acid.
  • the absorber 10 includes a column provided inside with a stack of Raschig rings 11 and is cooled externally by a double jacket 12 where a current of water circulates, which is admitted through an inlet pipe 13 and removed through an outlet pipe 14.
  • an inlet 15 is also provided for fresh acid and, at the lower part, a gas separator 16 which allows the incondensible gases to be removed through an outlet pipe 17 which have successively passed through the condenser 7 and the absorber 10.
  • the outlet 18 from the separator 16 is connected to the lower part of the dissolver tank 1, in order to obtain a simple gravity feed of fresh acid and to produce the attack on the bars of fuel which are contained therein.
  • the dissolver also comprises an inlet lock 19 for the introduction of metallic uranium and also an outlet pipe 20, to permit removal of uranyl nitrate in solution, which communicates with a pipe 21 acting as a thermosyphon and allowing the operation to proceed continuously with a homogeneous attaclc ng solution.
  • the pipes 26 and 21 are provided with valves 22, 23, 24 and 25, the valve 23 being provided for draining the apparatus and being closed during attack of the metal with the acid.
  • the above-described apparatus is thus constructed to carry out the continuous dissolution in nitric acid of rods of either natural or enriched metallic uranium or alloys of uranium, such as uranium/molybdenum and uranium/ chromium alloys, and also compounds of uranium and uranium cermets.
  • This dissolution takes place with permanent recombination, by oxidation and absorption, of the vapours evolved.
  • the solution of nitrate obtained flows from the dissolver through the outlet pipe 20, so providing a constant level inside the dissolver.
  • the attacking solution used is a liquor containing per litre, for example, about 4 to moles of free nitric acid and about 3 to 3.5 moles of uranyl nitrate.
  • the nitrate solution leaving the dissolver is more concentrated in uranyl nitrate than the solutions at present used. This feature is not critical however and it is possible subsequently to dilute this in the desired proportion in order to obtain the usual concentration.
  • the following examples all relate to the attack of uranium cylindrical rods 100 mm. in length and mm. in diameter.
  • uranium cylindrical rods 100 mm. in length and mm. in diameter.
  • the process of the invention it becomes possible to prepare for example a solution containing 3.5 moles of uranium per litre with a free acidity of 4.5 N.
  • the uranium hold-up in the receptacle is not more than 2.8 kg.
  • the velocity of penetration of the acid into the metal is then of the order of 1.5 mm. per hour, that is to say relatively very high.
  • the attack takes place under a pressure which is substantially the same as atmospheric pressure and at a temperature of about 114 C.
  • a solution of uranyl nitrate was continuously prepared containing 2.6 moles of uranium per litre with a free acidity of 4.5 N and using a uranium hold-up of only 4 kg. in the dissolution tank, the velocity of penetration of the metal by the acid being 0.8 mm. per hour.
  • the attack also took place under atmospheric pressure, but at a temperature of about 110 C.
  • the concentration of the attacking solution should preferably be from 2 to 5 moles of uranium per litre.
  • the concentration of the solution in free nitric acid, from a given threshold value has a much less marked influence upon the velocity of penetration of the acid (see FIG. 1).
  • This concentration can be selected within the range from 1 N to 11 N nitric acid, but generally it is desirable to operate in the range from 3 N to 5 N. Nitric acid losses caused during the dissolution are low and generally less than 5%.
  • the process according to the invention thus allows a considerably increased velocity of attack under continuous conditions (at least by 10 times), with respect to standard processes, at constant rates of introduction of uranium and nitric acid into the dissolver, which velocity of attack is maintained at a substantially constant value. Operation of the process takes place simply and economically, as it is not necessary to make use either of high pressure or of elevated temperatures, which consequently considerably diminishes the corrosion of the constructional materials. Also, because of the considerable decrease in hold-up, the volume of the apparatus can also be considerably reduced for the same overall velocity of dissolution. This reduction in volume, which is appreciable in any case, has a particular advantage in the case of dissolution of enriched uranium, because the risks of criticality are thus also diminished.
  • a process for the continuous dissolution of uranium containing articles comprising continuously subjecting said article to a homogenous nitric acid solution containing a constant elevated amount of from 2 to 5 moles of uranyl nitrate per liter, said solution being introduced at a constant rate and uranyl nitrate being continuously removed to provide said homogenous solution.
  • a process for the continuous dissolution of an uranium containing article as uranyl nitrate comprising continuously subjecting said article at atmospheric pressure and at a temperature of about 114 C. to a constant feed consisting essentially of nitric acid and uranium as a homogenous solution of 3.5 moles of uranium metal per liter of solution having a free nitric acidity of 4.5 N and continuously removing an uranyl nitrate solution, the speed of penetration of said solution into said article being about 1.5 mm. per hour.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
US28547763 1962-06-06 1963-06-04 Processes for the dissolution of uranium in nitric acid Expired - Lifetime US3243256A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR899924A FR1337268A (fr) 1962-06-06 1962-06-06 Perfectionnement aux procédés de dissolution de l'uranium dans l'acide nitrique

Publications (1)

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US3243256A true US3243256A (en) 1966-03-29

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Country Status (9)

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US (1) US3243256A (it)
BE (1) BE633313A (it)
CH (1) CH416586A (it)
DE (1) DE1192634B (it)
FR (1) FR1337268A (it)
GB (1) GB1001431A (it)
LU (1) LU43843A1 (it)
NL (1) NL293627A (it)
SE (1) SE334346B (it)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6033636A (en) * 1997-04-04 2000-03-07 Japan Nuclear Development Institute Method of recovering uranium and transuranic elements from spent nuclear fuel
CN105506274A (zh) * 2015-11-24 2016-04-20 中国原子能科学研究院 一种辐照低浓铀箔靶件铀箔溶解装置
US9793019B1 (en) 2014-03-26 2017-10-17 Savannah River Nuclear Solutions, Llc Low temperature chemical processing of graphite-clad nuclear fuels
CN115400618A (zh) * 2022-09-30 2022-11-29 中核四0四有限公司 一种铀矿石浓缩物溶解装置及方法

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2424964A1 (fr) * 1978-05-05 1979-11-30 Cogema Perfectionnements aux procedes de traitement de minerais uraniferes
GB2050039B (en) * 1979-04-30 1983-01-19 Atomic Energy Authority Uk Dissolving plutanium containing nuclear fuels

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2897047A (en) * 1954-02-26 1959-07-28 Wallace W Schulz Method of dissolving metallic uranium

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2897047A (en) * 1954-02-26 1959-07-28 Wallace W Schulz Method of dissolving metallic uranium

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6033636A (en) * 1997-04-04 2000-03-07 Japan Nuclear Development Institute Method of recovering uranium and transuranic elements from spent nuclear fuel
US9793019B1 (en) 2014-03-26 2017-10-17 Savannah River Nuclear Solutions, Llc Low temperature chemical processing of graphite-clad nuclear fuels
CN105506274A (zh) * 2015-11-24 2016-04-20 中国原子能科学研究院 一种辐照低浓铀箔靶件铀箔溶解装置
CN115400618A (zh) * 2022-09-30 2022-11-29 中核四0四有限公司 一种铀矿石浓缩物溶解装置及方法

Also Published As

Publication number Publication date
FR1337268A (fr) 1963-09-13
LU43843A1 (it) 1963-08-01
BE633313A (it) 1900-01-01
NL293627A (it) 1900-01-01
GB1001431A (en) 1965-08-18
CH416586A (fr) 1966-07-15
DE1192634B (de) 1965-05-13
SE334346B (it) 1971-04-26

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