EP0070213B1 - Procédé de traitement d'effluents aqueux basiques contenant du plutonium et éventuellement de l'uranium - Google Patents
Procédé de traitement d'effluents aqueux basiques contenant du plutonium et éventuellement de l'uranium Download PDFInfo
- Publication number
- EP0070213B1 EP0070213B1 EP82401143A EP82401143A EP0070213B1 EP 0070213 B1 EP0070213 B1 EP 0070213B1 EP 82401143 A EP82401143 A EP 82401143A EP 82401143 A EP82401143 A EP 82401143A EP 0070213 B1 EP0070213 B1 EP 0070213B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- plutonium
- effluents
- evaporation
- solution
- 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.)
- Expired
Links
- 229910052778 Plutonium Inorganic materials 0.000 title claims description 46
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 title claims description 46
- 229910052770 Uranium Inorganic materials 0.000 title claims description 14
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims description 14
- 238000000034 method Methods 0.000 title claims description 11
- 238000001704 evaporation Methods 0.000 claims description 23
- 230000008020 evaporation Effects 0.000 claims description 23
- 238000001556 precipitation Methods 0.000 claims description 14
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 claims description 8
- UIIMBOGNXHQVGW-UHFFFAOYSA-M Sodium bicarbonate Chemical compound [Na+].OC([O-])=O UIIMBOGNXHQVGW-UHFFFAOYSA-M 0.000 claims description 4
- 229910000029 sodium carbonate Inorganic materials 0.000 claims description 4
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 claims description 4
- 229910000030 sodium bicarbonate Inorganic materials 0.000 claims description 2
- 235000017557 sodium bicarbonate Nutrition 0.000 claims description 2
- 235000010344 sodium nitrate Nutrition 0.000 claims description 2
- 239000004317 sodium nitrate Substances 0.000 claims description 2
- 238000009835 boiling Methods 0.000 claims 1
- 239000000243 solution Substances 0.000 description 28
- 239000002244 precipitate Substances 0.000 description 8
- 239000011734 sodium Substances 0.000 description 7
- BVKZGUZCCUSVTD-UHFFFAOYSA-L Carbonate Chemical compound [O-]C([O-])=O BVKZGUZCCUSVTD-UHFFFAOYSA-L 0.000 description 6
- 239000000203 mixture Substances 0.000 description 5
- 239000003960 organic solvent Substances 0.000 description 4
- 238000005406 washing Methods 0.000 description 4
- BVKZGUZCCUSVTD-UHFFFAOYSA-M Bicarbonate Chemical compound OC([O-])=O BVKZGUZCCUSVTD-UHFFFAOYSA-M 0.000 description 3
- 229910002651 NO3 Inorganic materials 0.000 description 3
- 239000007864 aqueous solution Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000002474 experimental method Methods 0.000 description 3
- 238000000605 extraction Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 238000012958 reprocessing Methods 0.000 description 3
- 229910052774 Proactinium Inorganic materials 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 239000002904 solvent Substances 0.000 description 2
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical group CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 description 2
- 241000410518 Cyrano Species 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 150000004649 carbonic acid derivatives Chemical class 0.000 description 1
- 230000000536 complexating effect Effects 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 239000007857 degradation product Substances 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 230000007062 hydrolysis Effects 0.000 description 1
- 238000006460 hydrolysis reaction Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
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, which can be used in particular for treating aqueous effluents obtained by alkaline washing of the organic solvents used in nuclear fuel reprocessing plants irradiated.
- organic solvents are generally used to extract plutonium and uranium from nitric solutions for dissolving used 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 especially plutonium, thanks to the complexing properties of the carbonate ion.
- 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 either plutonium or plutonium and uranium in solution, 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 said effluents are concentrated by evaporation under reduced pressure, at a temperature below 80 ° C to avoid precipitation of plutonium.
- the effluent is evaporated at a pressure of 67,500 to 72,900 Pa.
- 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 ensure a re-solution of the precipitated plutonium.
- the temperature used during evaporation, the precipitation of plutonium is avoided and it is thus possible to obtain solutions concentrated in plutonium.
- the method 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 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 plutonium precipitates at a rate of 1% of the total plutonium.
- 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)
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 EP0070213A1 (fr) | 1983-01-19 |
| EP0070213B1 true EP0070213B1 (fr) | 1986-01-02 |
Family
ID=9259833
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP82401143A Expired EP0070213B1 (fr) | 1981-06-24 | 1982-06-22 | Procédé de traitement d'effluents aqueux basiques contenant du plutonium et éventuellement de l'uranium |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US4481135A (enrdf_load_stackoverflow) |
| EP (1) | EP0070213B1 (enrdf_load_stackoverflow) |
| JP (1) | JPS586494A (enrdf_load_stackoverflow) |
| DE (1) | DE3268264D1 (enrdf_load_stackoverflow) |
| FR (1) | FR2508693A1 (enrdf_load_stackoverflow) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3639066A1 (de) * | 1986-11-14 | 1988-05-19 | Kernforschungsz Karlsruhe | Verfahren zur verbesserung der kritikalitaetssicherheit in einem fluessig-fluessig-extraktionsprozess fuer bestrahlte kernbrenn- und/oder brutstoffe |
| 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 |
Family Cites Families (8)
| 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 |
| BE630664A (enrdf_load_stackoverflow) * | 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 |
| US4208377A (en) * | 1978-07-25 | 1980-06-17 | The United States Of America As Represented By The United States Department Of Energy | Process for recovering actinide values |
-
1981
- 1981-06-24 FR FR8112408A patent/FR2508693A1/fr active Granted
-
1982
- 1982-06-17 US US06/389,281 patent/US4481135A/en not_active Expired - Lifetime
- 1982-06-22 DE DE8282401143T patent/DE3268264D1/de not_active Expired
- 1982-06-22 JP JP57106997A patent/JPS586494A/ja active Granted
- 1982-06-22 EP EP82401143A patent/EP0070213B1/fr not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS586494A (ja) | 1983-01-14 |
| DE3268264D1 (en) | 1986-02-13 |
| EP0070213A1 (fr) | 1983-01-19 |
| US4481135A (en) | 1984-11-06 |
| FR2508693A1 (fr) | 1982-12-31 |
| JPH0129280B2 (enrdf_load_stackoverflow) | 1989-06-08 |
| FR2508693B1 (enrdf_load_stackoverflow) | 1983-10-07 |
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