GB2144111A - Extraction of metal ions - Google Patents

Extraction of metal ions Download PDF

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Publication number
GB2144111A
GB2144111A GB08417696A GB8417696A GB2144111A GB 2144111 A GB2144111 A GB 2144111A GB 08417696 A GB08417696 A GB 08417696A GB 8417696 A GB8417696 A GB 8417696A GB 2144111 A GB2144111 A GB 2144111A
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GB
United Kingdom
Prior art keywords
thorium
uranium
nitric acid
extraction
metal ions
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
GB08417696A
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GB8417696D0 (en
GB2144111B (en
Inventor
Harry Eccles
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Sellafield Ltd
Original Assignee
British Nuclear Fuels PLC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from GB838319838A external-priority patent/GB8319838D0/en
Application filed by British Nuclear Fuels PLC filed Critical British Nuclear Fuels PLC
Priority to GB08417696A priority Critical patent/GB2144111B/en
Publication of GB8417696D0 publication Critical patent/GB8417696D0/en
Publication of GB2144111A publication Critical patent/GB2144111A/en
Application granted granted Critical
Publication of GB2144111B publication Critical patent/GB2144111B/en
Expired legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/12Processing by absorption; by adsorption; by ion-exchange
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01FCOMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
    • C01F15/00Compounds of thorium
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00Compounds of transuranic elements
    • C01G56/001Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • C01G56/002Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange by adsorption or by ion-exchange on a solid support
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/42Treatment or purification of solutions, e.g. obtained by leaching by ion-exchange extraction
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02PCLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00Technologies related to metal processing
    • Y02P10/20Recycling

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  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

A method for extracting metal ions having a high charge and a small ionic radius and in the tetravalent state, from acid liquors involves the step of contacting the liquor with a chelating aminophosphonic acid ion exchange resin, known per se. The method is particularly effective for extracting thorium and other radionuclides from nitric acid raffinates arising during the production of pure uranium for nuclear fuel from uranium ore concentrates. The method can also be applied to the removal of parts per million amounts of actinides such as plutonium, neptunium, protoactinium and uranium from acid liquors destined for disposal or storage.

Description

SPECIFICATION Extraction of some metal ions from nitric acid liquors This invention relates to the extraction of some metal ions from acid liquors.
In the production of nuclear fuel material several sequential processes are necessary to convert uranium ore concentrates to other uranic compounds. In one of these processes the uranium ore concentrate is dissolved in nitric acid and the uranium in the resultant uranyl nitrate liquor is then separated from the impurities which are liberated from the ore concentrate with the uranium, predominantly as nitrates. The separation is effected by a solvent extraction procedure from which an acidic raffinate rich in nitric acid but contaminated with the impurities is usually discarded. The major impurities are the alkali and alkaline earth metals, aluminium, some first and second row transition metals, non-uranic radionuclides and various anionic species such as fluorides and sulphates.The radionuclides are principally uranium daughters (protoactinium 234 and thorium 234), thorium 230 and the natural thorium isotope Th 232.
The present invention in one of its aspects seeks to remove such radionuclides from the nitric acid raffinate so that, after further treatment, the nitric acid can be recycled to the dissolution process.
According to the present invention, metal ions having a high charge and a small ionic radius and in the tetravalent state can be extracted from acidic liquors by contracting the liquor with a chelating aminophosphonic acid ion exchange resin, known per se.
One example of a metal ion as specified in the preceding paragraph is thorium. Another is protoactinium. The said resin can therefore be employed to remove these radionuclides from nitric acid raffinates as aforesaid. An advantage of a chelating amino-phosphonic acid resin is that its ability to absorb thorium and protoactinium from a plant nitric acid raffinate is not normally impaired by nitric acid concentration nor the presence of foreign ions such as sodium, calcium or sulphate. Indeed, it has been established that high nitric acid values (6M) and higher temperatures (of approximately 50"C) can improve the distribution of thorium.This advantage is shown by the results obtained by determining the thorium distribution (KdTh) and the thorium capacity of the resin Duolite ES 467 (obtainable from Dia-Prosim Ltd, Hounslow, Middlesex) using a plant nitric acid raffinate of which some of the major constituents are given in the following Table I.
TABLE I Composition of Plant Raffinate Element Composition Nitric acid acidity 9.6% w/v (1.52M) Total Nitrate 11.0% w/v Sulphate 0.44% w/v Fluoride 0.11 % w/v Aluminium 880 mg/l Iron (total) 720 mg/l Calcium 700 mg/i Sodium 450 mg/l Magnesium 200 mg/l Potassium 140 mg/l Thorium 130 mg/l Results are depicted graphically in the accompanying Figs. and in Tables II and Ill. Fig. 1 shows the effect of varying the nitric acid concentration and temperature. Fig. 2 shows the effect of thorium concentration. The influence of sodium, calcium and ferric ions on the thorium distribution is indicated in the following Table II and the effect of sulphate concentration in the following Table Ill.
TABLE II The Effect of Sodium, Calcium and Iron (111) Concentration of KdTh Value Metal ion in equilibrium with the Resin Na Ca Fe Initial Metal Ion 0.45 1.2 5.0 0.78 1.9 6.5 0.72 1.8 5.8 concentration g/l KdTh Value 176 162 200 176 212 200 176 70 13 TABLE 111 The Effect of Sulphate Concentration on Kd Values Initial Sulphate concentration g/l Fe Ca Th 4.4 7 1 176 13.0 4 2 171 38.0 2 2 186 For the results in Fig. 1 the nitric acid value of the plant raffinate as received was reduced using the ion-retardation resin AG11-A8 from Bio-Rad Laboratories and increased by the addition of the appropriate quantity of concentrated acid. 10g of the nitric acid pre-conditioned resin was equilibrated at a constant temperature ( + 2"C) with 100 ml of the appropriate raffinate solutions for 1 hour in a stoppered flask and the distribution values of thorium determined as beta activity, the procedure being carried out at 25, 35, 45 and 55"C. For the results in Fig. 2 10g of preconditioned resin was equilibrated at 25 + 2"C with successive 100 ml portions of as received plant raffinate until the beta activity of the equilibrated sample was constant. The beta activity removed was converted to the corresponding thorium value. For the results in Tables II and Ill appropriate amounts of sodium nitrate, calcium nitrate, ferric nitrate and sulphuric acid were added to portions of the plant raffinate and the procedure followed as for Fig. 1, the temperature being 25 + 2"C.
Thorium may be eluted from the resin with 0.5M ammonium carbonate.
Further examples of metal ions as aforesaid are actinides such as plutonium, neptunium and uranium when in tetravalent state. The employment of a resin as aforesaid is advantageous in its ability to remove small quantities, in the parts per million range, of such metals from waste acidic liquors before discharge or storage.

Claims (5)

1. A method of extraction from acidic liquors of metal ions having a high charge and a small ionic radius and in the tetravalent state, including the step of contacting the liquor with a chelating aminophosphonic acid ion exchange resin, known per se.
2. A method according to claim 1, wherein the acidic liquor is a nitric acid raffinate, and the metal ion for extraction is thorium.
3. A method according to claim 2, including the additional step of eluting thorium from the said resin employing ammonium carbonate.
4. A method according to claim 1, wherein the acidic liquor is a nitric acid raffinate, and the metal ion is or are one or more of the actinides plutonium, neptunium and uranium, all in the tetravalent state and present in the raffinate in concentrations of the order of parts per million.
5. A method of extraction from acidic liquors of metal ions having a high charge and a small ionic radius and in the tetravalent state, substantially as herein described.
GB08417696A 1983-07-22 1984-07-11 Extraction of metal ions Expired GB2144111B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB08417696A GB2144111B (en) 1983-07-22 1984-07-11 Extraction of metal ions

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB838319838A GB8319838D0 (en) 1983-07-22 1983-07-22 Extraction of thorium from nitric acid liquors
GB08417696A GB2144111B (en) 1983-07-22 1984-07-11 Extraction of metal ions

Publications (3)

Publication Number Publication Date
GB8417696D0 GB8417696D0 (en) 1984-08-15
GB2144111A true GB2144111A (en) 1985-02-27
GB2144111B GB2144111B (en) 1986-12-17

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Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0209048A1 (en) * 1985-07-10 1987-01-21 Hitachi, Ltd. Process and apparatus for cleaning nuclear reactor cooling water
EP0532919A1 (en) * 1991-09-19 1993-03-24 Siemens Power Corporation Method for removing a heavy metal from a waste stream
EP0621801A1 (en) * 1991-10-10 1994-11-02 Brigham Young University Aminoalkylphosphonic acid containing ligands attached to solid supports for removal of metal ions
AT401122B (en) * 1994-05-09 1996-06-25 Oesterr Forsch Seibersdorf Method for stabilizing ion exchange resins loaded with radioactive materials, and products stabilized in such a way
EP1085527A2 (en) * 1999-09-17 2001-03-21 Siemens Power Corporation Treatment process for removing radioactive thorium from solvent extraction liquid effluent
RU2454742C1 (en) * 2010-12-23 2012-06-27 Федеральное государственное унитарное предприятие "Научно-производственное объединение "Радиевый институт им. В.Г. Хлопина" Method for processing of spent nuclear fuel of nuclear power plants
US8557201B1 (en) 2012-08-08 2013-10-15 Rohm And Haas Company Method for the recovery of uranium from pregnant liquor solutions
RU2638543C1 (en) * 2017-02-14 2017-12-14 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Method of producing mixed uranium-plutonium oxide

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB972943A (en) * 1962-10-08 1964-10-21 Dow Chemical Co Method for separating thorium and yttrium values
GB1430776A (en) * 1972-09-09 1976-04-07 Bayer Ag Process for separating the actinide elements

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB972943A (en) * 1962-10-08 1964-10-21 Dow Chemical Co Method for separating thorium and yttrium values
GB1430776A (en) * 1972-09-09 1976-04-07 Bayer Ag Process for separating the actinide elements

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4880595A (en) * 1985-07-10 1989-11-14 Hitachi, Ltd. Process and apparatus for cleaning nuclear reactor cooling water
EP0209048A1 (en) * 1985-07-10 1987-01-21 Hitachi, Ltd. Process and apparatus for cleaning nuclear reactor cooling water
US6165367A (en) * 1991-09-19 2000-12-26 Siemens Power Corporation Method for removing a heavy metal from a waste stream
EP0532919A1 (en) * 1991-09-19 1993-03-24 Siemens Power Corporation Method for removing a heavy metal from a waste stream
EP0621801A1 (en) * 1991-10-10 1994-11-02 Brigham Young University Aminoalkylphosphonic acid containing ligands attached to solid supports for removal of metal ions
EP0621801A4 (en) * 1991-10-10 1995-04-26 Univ Brigham Young Aminoalkylphosphonic acid containing ligands attached to solid supports for removal of metal ions.
AT401122B (en) * 1994-05-09 1996-06-25 Oesterr Forsch Seibersdorf Method for stabilizing ion exchange resins loaded with radioactive materials, and products stabilized in such a way
EP1085527A2 (en) * 1999-09-17 2001-03-21 Siemens Power Corporation Treatment process for removing radioactive thorium from solvent extraction liquid effluent
EP1085527A3 (en) * 1999-09-17 2004-06-23 Framatome ANP, Inc. Treatment process for removing radioactive thorium from solvent extraction liquid effluent
US6991731B2 (en) 1999-09-17 2006-01-31 Framatome Anp Inc. Treatment process for removing radioactive thorium from solvent extraction liquid effluent
RU2454742C1 (en) * 2010-12-23 2012-06-27 Федеральное государственное унитарное предприятие "Научно-производственное объединение "Радиевый институт им. В.Г. Хлопина" Method for processing of spent nuclear fuel of nuclear power plants
US8557201B1 (en) 2012-08-08 2013-10-15 Rohm And Haas Company Method for the recovery of uranium from pregnant liquor solutions
RU2638543C1 (en) * 2017-02-14 2017-12-14 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Method of producing mixed uranium-plutonium oxide

Also Published As

Publication number Publication date
GB8417696D0 (en) 1984-08-15
GB2144111B (en) 1986-12-17

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PE20 Patent expired after termination of 20 years

Effective date: 20040710