EP0033444B1 - Procédé de récupération de l'uranium et/ou du plutonium à partir de solutions contenant une haute charge de sel - Google Patents

Procédé de récupération de l'uranium et/ou du plutonium à partir de solutions contenant une haute charge de sel Download PDF

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Publication number
EP0033444B1
EP0033444B1 EP81100234A EP81100234A EP0033444B1 EP 0033444 B1 EP0033444 B1 EP 0033444B1 EP 81100234 A EP81100234 A EP 81100234A EP 81100234 A EP81100234 A EP 81100234A EP 0033444 B1 EP0033444 B1 EP 0033444B1
Authority
EP
European Patent Office
Prior art keywords
plutonium
uranium
solution
starting solution
solutions
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.)
Expired
Application number
EP81100234A
Other languages
German (de)
English (en)
Other versions
EP0033444A1 (fr
Inventor
Volker Dr. Schneider
Gerhard Margraf
Wolf-Günther Dr. Druckenbrodt
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.)
Alkem GmbH
Original Assignee
Alkem GmbH
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
Application filed by Alkem GmbH filed Critical Alkem GmbH
Publication of EP0033444A1 publication Critical patent/EP0033444A1/fr
Application granted granted Critical
Publication of EP0033444B1 publication Critical patent/EP0033444B1/fr
Expired legal-status Critical Current

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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
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265—Obtaining 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
    • 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
    • C22B60/04—Obtaining plutonium

Definitions

  • the invention relates to a method for recovering the heavy metals uranium and / or plutonium from a starting solution, which is carried out to absorb UO 2 2+ and PuO 2 2+ ions over a macroporous, copolymerized resin bed provided with a phosphorus compound as active substance. from which these heavy metal ions are eluted with nitric acid.
  • the invention is based on the principle of using the salts and the uranium and plutonium ions, which are contained in filtrates from conversion processes for producing UO 2 or U / PuO 2 , with the least possible losses at an optimally low cost.
  • a method of the type mentioned at the outset is characterized according to the invention in that, as the starting solution, filtrates from conversion processes for producing UO 2 or U / PuO 2 , which have a pH of ⁇ 3 by adding 5 to 10 m of HNO a were set, and 3 to 6 molar nitric acid are used in a temperature range up to 80 ° C for the elution, and that the residual solution formed after passing the starting solution over the resin bed and the evaporated eluate are returned to conversion processes.
  • the invention makes use of the knowledge that a high salt load in the starting solution does not in any way impair the effectiveness of the macroporous resin bed in absorbing uranium and plutonium ions if these heavy metal ions are only present in the starting solution in a low concentration.
  • the heavy metals uranium and / or plutonium in the starting solution are advantageously oxidized into the hexavalent stage.
  • the mother liquor coming from a filtration process is introduced into the reaction vessel 1 via the line 13 and the valve 15. It contains approx. 400 g / I ammonium salts and approx. 1 g U (VI) / Pu (VI) per liter. 5-10 molar nitric acid is then added via line 14 and valve 16 until the solution has a pH ⁇ 3.
  • An agitator 11 ensures that the contents of the container are always mixed uniformly.
  • the CO 2 formed during the reaction is discharged via line 17, a cold trap 19 and a filter 18.
  • the container 1 is cooled via the device 12 to remove the heat of reaction.
  • the solution is fed via line 51, the pump 5, the line 52, the valves 53, 54 and the line 55 to the fixed bed extraction column 4.
  • this column is filled with an absorber resin, for example a macroporous copolymerized resin with a phosphorus compound as the active substance.
  • the specific load when loading this column 4 with uranium / plutonium or flow rate is about 1-10 bed volumes per hour.
  • the mother liquor freed of uranium and plutonium in this way reaches line 2, line 58, line 58 and line 22 as well as valve 22 and 24 to tank 2, it consists practically of an NH 4 NO 3 solution and is then via line 25 and the valve 26 are returned to the conversion process.
  • the adsorbed heavy metals uranium and plutonium are then eluted by rinsing the bed with approx. 3-6 molar nitric acid in a temperature range of 30 ⁇ 50 ° C ⁇ adjustable via the heater 41 or 12, this acid in an amount of about 3 -5 bed volumes per hour is passed through the column.
  • This elution takes place in the reverse flow direction to the loading, that is to say the valve 53 is switched to the line 56, and likewise the valve 58, so that this nitric acid enters the fixed bed column 4 from above via the line 57.
  • the fissile material is enriched in the eluate to a concentration of 10-20 g / l.
  • This eluate passes via line 55, the appropriately converted valve 54 to line 21 and from there into container 2, the valve 26 of which is closed. It then passes via line 27 and the open valve 28 into the evaporator 3, where it is enriched to a concentration of 300 to 400 g / l of fission material and returned to the conversion process via line 32.
  • the evaporator is of course provided for this purpose with a heating device or with a heatable double jacket in the usual way.
  • this method can be carried out not only discontinuously, as shown here in the example, but also continuously.
  • Another application of the process according to the invention - including the oxidation - is also in the Pu separation from the filtrate concentrates of the oxalate process according to DE-OS 2 624 990.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)

Claims (2)

1. Procédé de récupération des métaux lourds que sont l'uranium et/ou le plutonium dans une solution de départ, qui, pour l'absorption des ions UO2 2+ et PuO2 2+, est envoyée sur un lit de résine macroporeuse, copolymérisée, munie d'un composé phosphoré servant de substance active et dont les ions de métaux lourds sont élués par de l'acide nitrique, caractérisé en ce qu'il consiste à utiliser, dans une plage de températures allant jusqu'à 80°C, comme solution de départ, des filtrats provenant de processus de conversion destinés à la préparation de UO2 et de U/PuO2, qui ont été réglés à une valeur de pH inférieure à 3 par addition de HNOa 5 à 10 m, ainsi que, pour l'élu- tion, de l'acide nitrique 3 à 6 molaire et à recycler au processus de conversion la solution résiduelle qui se forme, après passage de la solution de départ sur le lit de résine, ainsi que l'éluat concentré par évaporation.
2. Procédé suivant la revendication 1, caractérisé en ce qu'il consiste à oxyder à l'état hexavalent les métaux lourds que sont l'uranium et/ou le plutonium de la solution de départ.
EP81100234A 1980-01-29 1981-01-14 Procédé de récupération de l'uranium et/ou du plutonium à partir de solutions contenant une haute charge de sel Expired EP0033444B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3003087 1980-01-29
DE19803003087 DE3003087A1 (de) 1980-01-29 1980-01-29 Verfahren zur rueckgewinnung von uran und/oder plutonium aus loesungen mit hoher salzfracht

Publications (2)

Publication Number Publication Date
EP0033444A1 EP0033444A1 (fr) 1981-08-12
EP0033444B1 true EP0033444B1 (fr) 1984-12-05

Family

ID=6093161

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81100234A Expired EP0033444B1 (fr) 1980-01-29 1981-01-14 Procédé de récupération de l'uranium et/ou du plutonium à partir de solutions contenant une haute charge de sel

Country Status (3)

Country Link
EP (1) EP0033444B1 (fr)
JP (1) JPS579849A (fr)
DE (2) DE3003087A1 (fr)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
HU185105B (en) * 1982-06-10 1984-12-28 Magyar Asvanyolaj Es Foeldgaz Method for producing waste solution concentrates of atomic power station having high salt concantration
DE3718338A1 (de) * 1987-06-01 1989-01-05 Karlsruhe Wiederaufarbeit Verfahren und vorrichtung zur loesungsmittelwaesche bei der wiederaufarbeitung von bestrahlten kernbrennstoffen

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB812815A (en) * 1954-12-08 1959-04-29 Permutit Co Ltd Improvements relating to the recovery of uranium from solutions
GB801743A (en) * 1954-05-18 1958-09-17 Atomic Energy Authority Uk Extraction of plutonium and uranium
DE2244306A1 (de) * 1972-09-09 1974-03-21 Bayer Ag Verfahren zur trennung der actinidenelemente
DE2733396C2 (de) * 1977-07-23 1979-09-06 Kernforschungsanlage Juelich Gmbh, 5170 Juelich Verfahren und Vorrichtung zum Beladen von Kernen schwachsaurer Kationenaustauscherharze mit Uranylionen

Also Published As

Publication number Publication date
JPS579849A (en) 1982-01-19
DE3003087A1 (de) 1981-07-30
DE3167517D1 (en) 1985-01-17
EP0033444A1 (fr) 1981-08-12
JPS6366372B2 (fr) 1988-12-20

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