EP0070213A1 - Verfahren zur Behandlung von basischen Abwässern, die Plutonium und gegebenenfalls Uranium enthalten - Google Patents

Verfahren zur Behandlung von basischen Abwässern, die Plutonium und gegebenenfalls Uranium enthalten Download PDF

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Publication number
EP0070213A1
EP0070213A1 EP82401143A EP82401143A EP0070213A1 EP 0070213 A1 EP0070213 A1 EP 0070213A1 EP 82401143 A EP82401143 A EP 82401143A EP 82401143 A EP82401143 A EP 82401143A EP 0070213 A1 EP0070213 A1 EP 0070213A1
Authority
EP
European Patent Office
Prior art keywords
plutonium
effluents
evaporation
temperature
uranium
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
EP82401143A
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English (en)
French (fr)
Other versions
EP0070213B1 (de
Inventor
Alain Aspart
Bernard Guillaume
Jean-Paul Moulin
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of EP0070213A1 publication Critical patent/EP0070213A1/de
Application granted granted Critical
Publication of EP0070213B1 publication Critical patent/EP0070213B1/de
Expired legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/08—Processing by evaporation; by distillation
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S159/00—Concentrating evaporators
    • Y10S159/12—Radioactive

Definitions

  • the present invention relates to a process for treating basic aqueous effluents containing plutonium and optionally uranium, usable in particular for treating aqueous effluents obtained by alkaline washing of organic solvents used in nuclear fuel reprocessing installations irradiated.
  • organic solvents are generally used to extract plutonium and uranium from nitric solutions for dissolving spent fuel. After this extraction step in the organic solvent, the uranium and plutonium are recovered by selective re-extraction in aqueous solutions, then the organic solvent is treated to purify and decontaminate it before recycling it at the extraction stage of the 'uranium and plutonium.
  • the purification treatment of the solvent comprises an alkaline washing step carried out for example by means of a sodium carbonate solution.
  • this alkaline washing step with a sodium carbonate solution makes it possible, on the one hand, to extract from the aqueous solution, dibutylphosphoric acid [(DBP) - H + ] which is the main degradation product of tributyl phosphate and, on the other hand, to keep heavy metal ions in aqueous solution, in particular uranium, zirconium and in particular plutonium, thanks to the complexing properties of the ion carbonate.
  • DBP dibutylphosphoric acid
  • Radioactive effluents are thus obtained, following this alkaline washing step, which contain traces of plutonium and uranium in solution.
  • the present invention specifically relates to a process for treating basic aqueous effluents containing plutonium and optionally uranium, which makes it possible to reduce the volume of these effluents while avoiding precipitation of the plutonium.
  • the process of the invention is characterized in that the said effluents are concentrated by evaporation under reduced pressure, at a temperature such that precipitation of the plutonium is avoided.
  • evaporation is carried out at a temperature below 80 ° C., for example at a temperature between 50 and 80 ° C.
  • the solubility of plutonium in carbonate medium decreases sharply when the temperature reaches 90 ° C, which is probably due to the fact that the rise in temperature promotes the displacement of plutonium from its carbonate complexes by hydrolysis.
  • the dissolution rate of the plutonium precipitate thus formed is undoubtedly too slow when cold in carbonate solutions. This does not allow a re-solution of the precipitated plutonium to be ensured.
  • the temperature used during evaporation, the precipitation of plutonium is avoided and it is thus possible to obtain solutions concentrated in plutonium.
  • the process of the invention is particularly applicable to the treatment of aqueous effluents containing sodium carbonate, and optionally sodium hydrogencarbonate and sodium nitrate.
  • evaporation is carried out under reduced pressure by heating the solution for a period such that a concentration factor of the effluents is obtained at least equal to 6.
  • This example relates to the treatment of basic aqueous effluents having the following composition:
  • This solution is concentrated by evaporation, operating under a pressure of 70875 Pa, at a temperature of 60 ° C., and the evaporation is continued until concentration factors ranging from 2 to 8 are obtained.
  • the concentration of the solution which corresponds to this concentration factor of 6 is approximately as follows:
  • the plutonium precipitates at a rate of 1% of the total plutonium.
  • This example concerns the treatment of basic effluents obtained during the experimental reprocessing of nuclear fuels of the PWR (Borselle) type in the Cyrano chain. These effluents have the following composition: and they have a 5y activity of 100 ⁇ Ci.l -1 .
  • the concentration factor reaches the value 10
  • the concentration factor reaches the value 10
  • the formation of a slight precipitate is observed.
  • the latter does not contain plutonium to the accuracy of the measurements.
  • the precipitate which forms contains 6% of the total plutonium.
  • the concentration of the effluents by evaporation under reduced pressure at a temperature below 80 ° C., makes it possible to carry out the concentration of these effluents until a concentration factor is obtained at less than 6 without precipitation of plutonium.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Polysaccharides And Polysaccharide Derivatives (AREA)
EP82401143A 1981-06-24 1982-06-22 Verfahren zur Behandlung von basischen Abwässern, die Plutonium und gegebenenfalls Uranium enthalten Expired EP0070213B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8112408 1981-06-24
FR8112408A FR2508693A1 (fr) 1981-06-24 1981-06-24 Procede de traitement d'effluents aqueux basiques contenant du plutonium et eventuellement de l'uranium

Publications (2)

Publication Number Publication Date
EP0070213A1 true EP0070213A1 (de) 1983-01-19
EP0070213B1 EP0070213B1 (de) 1986-01-02

Family

ID=9259833

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82401143A Expired EP0070213B1 (de) 1981-06-24 1982-06-22 Verfahren zur Behandlung von basischen Abwässern, die Plutonium und gegebenenfalls Uranium enthalten

Country Status (5)

Country Link
US (1) US4481135A (de)
EP (1) EP0070213B1 (de)
JP (1) JPS586494A (de)
DE (1) DE3268264D1 (de)
FR (1) FR2508693A1 (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0267393A1 (de) * 1986-11-14 1988-05-18 Kernforschungszentrum Karlsruhe Gmbh Verfahren zur Verbesserung der Kritikalitätssicherheit in einem Flüssig-Flüssig-Extraktionsprozess für bestrahlte Kernbrenn- und/oder Brutstoffe

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5253597A (en) * 1992-06-18 1993-10-19 Chemical Waste Management, Inc. Process for separating organic contaminants from contaminated soils and sludges
US7669349B1 (en) 2004-03-04 2010-03-02 TD*X Associates LP Method separating volatile components from feed material

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1228009B (de) * 1961-02-09 1966-11-03 Atomkraftwerk Rheinsberg Mit B Verfahren zum Beseitigen von radioaktiven Verunreinigungen aus Fluessigkeiten
GB2027257A (en) * 1978-07-25 1980-02-13 Us Energy Recovering actinide valves

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL291224A (de) * 1962-04-06
US3361649A (en) * 1965-04-05 1968-01-02 American Mach & Foundry Method and apparatus for distillation of waste liquids and separate recovery of solvent and solute
DE1228099B (de) * 1965-07-24 1966-11-03 Fichtel & Sachs Ag Baumentastungsgeraet
US4108718A (en) * 1976-01-27 1978-08-22 Purdue Research Foundation Vapor filtration process and system
US4197197A (en) * 1976-06-25 1980-04-08 Abaeva Tatyana V Method for removing oil film from water surface
JPS5423900A (en) * 1977-07-25 1979-02-22 Mitsubishi Metal Corp Recovering regeneration method of radioactive retreating waste organic solvent

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1228009B (de) * 1961-02-09 1966-11-03 Atomkraftwerk Rheinsberg Mit B Verfahren zum Beseitigen von radioaktiven Verunreinigungen aus Fluessigkeiten
GB2027257A (en) * 1978-07-25 1980-02-13 Us Energy Recovering actinide valves

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0267393A1 (de) * 1986-11-14 1988-05-18 Kernforschungszentrum Karlsruhe Gmbh Verfahren zur Verbesserung der Kritikalitätssicherheit in einem Flüssig-Flüssig-Extraktionsprozess für bestrahlte Kernbrenn- und/oder Brutstoffe
US4871478A (en) * 1986-11-14 1989-10-03 Kernforschungszentrum Karlsruhe Gmbh Method of improving the criticality safety in a liquid-liquid extraction process for spent nuclear fuel or breeder reactor materials

Also Published As

Publication number Publication date
DE3268264D1 (en) 1986-02-13
EP0070213B1 (de) 1986-01-02
FR2508693B1 (de) 1983-10-07
JPH0129280B2 (de) 1989-06-08
US4481135A (en) 1984-11-06
JPS586494A (ja) 1983-01-14
FR2508693A1 (fr) 1982-12-31

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