EP3365897A1 - Utilisation d'aldoximes comprenant au moins cinq atomes de carbone comme agents anti-nitreux dans des opérations de désextraction réductrice du plutonium - Google Patents
Utilisation d'aldoximes comprenant au moins cinq atomes de carbone comme agents anti-nitreux dans des opérations de désextraction réductrice du plutoniumInfo
- Publication number
- EP3365897A1 EP3365897A1 EP16784854.8A EP16784854A EP3365897A1 EP 3365897 A1 EP3365897 A1 EP 3365897A1 EP 16784854 A EP16784854 A EP 16784854A EP 3365897 A1 EP3365897 A1 EP 3365897A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- oxime
- plutonium
- uranium
- organic
- use according
- 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
Links
- 229910052778 Plutonium Inorganic materials 0.000 title claims abstract description 68
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 title claims abstract description 68
- GQPLMRYTRLFLPF-UHFFFAOYSA-N nitrous oxide Inorganic materials [O-][N+]#N GQPLMRYTRLFLPF-UHFFFAOYSA-N 0.000 title claims abstract description 33
- 125000004432 carbon atom Chemical group C* 0.000 title claims abstract description 15
- 230000002829 reductive effect Effects 0.000 title abstract description 23
- 238000000605 extraction Methods 0.000 title abstract description 19
- 238000000034 method Methods 0.000 claims abstract description 34
- 239000003795 chemical substances by application Substances 0.000 claims abstract description 24
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims abstract description 16
- 239000012074 organic phase Substances 0.000 claims description 103
- 239000008346 aqueous phase Substances 0.000 claims description 100
- HNVACBPOIKOMQP-UHFFFAOYSA-N uranium(4+) Chemical group [U+4] HNVACBPOIKOMQP-UHFFFAOYSA-N 0.000 claims description 59
- YOIWSDLNGMVRLR-SREVYHEPSA-N (NZ)-N-hexylidenehydroxylamine Chemical compound CCCCC\C=N/O YOIWSDLNGMVRLR-SREVYHEPSA-N 0.000 claims description 50
- YUKIAUPQUWVLBK-UHFFFAOYSA-N n-pentylidenehydroxylamine Chemical group CCCCC=NO YUKIAUPQUWVLBK-UHFFFAOYSA-N 0.000 claims description 49
- FZENGILVLUJGJX-NSCUHMNNSA-N (E)-acetaldehyde oxime Chemical compound C\C=N\O FZENGILVLUJGJX-NSCUHMNNSA-N 0.000 claims description 41
- 229910052770 Uranium Inorganic materials 0.000 claims description 33
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical group [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 33
- 230000008569 process Effects 0.000 claims description 31
- 150000002923 oximes Chemical class 0.000 claims description 28
- 230000003647 oxidation Effects 0.000 claims description 25
- 238000007254 oxidation reaction Methods 0.000 claims description 25
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 19
- 229910017604 nitric acid Inorganic materials 0.000 claims description 19
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims description 16
- ZLYXMBXMECZBSN-UHFFFAOYSA-N [Pu+3] Chemical compound [Pu+3] ZLYXMBXMECZBSN-UHFFFAOYSA-N 0.000 claims description 13
- 239000003638 chemical reducing agent Substances 0.000 claims description 13
- 239000003085 diluting agent Substances 0.000 claims description 5
- 238000000926 separation method Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 5
- CRJZNQFRBUFHTE-UHFFFAOYSA-N hydroxylammonium nitrate Chemical compound O[NH3+].[O-][N+]([O-])=O CRJZNQFRBUFHTE-UHFFFAOYSA-N 0.000 claims description 4
- 229910019142 PO4 Inorganic materials 0.000 claims description 2
- 125000000217 alkyl group Chemical group 0.000 claims description 2
- 150000002443 hydroxylamines Chemical class 0.000 claims description 2
- SQZYOZWYVFYNFV-UHFFFAOYSA-L iron(2+);disulfamate Chemical compound [Fe+2].NS([O-])(=O)=O.NS([O-])(=O)=O SQZYOZWYVFYNFV-UHFFFAOYSA-L 0.000 claims description 2
- LNOPIUAQISRISI-UHFFFAOYSA-N n'-hydroxy-2-propan-2-ylsulfonylethanimidamide Chemical compound CC(C)S(=O)(=O)CC(N)=NO LNOPIUAQISRISI-UHFFFAOYSA-N 0.000 claims description 2
- 239000010452 phosphate Substances 0.000 claims description 2
- 125000001183 hydrocarbyl group Chemical group 0.000 claims 2
- 239000003758 nuclear fuel Substances 0.000 abstract description 4
- OAKJQQAXSVQMHS-UHFFFAOYSA-N Hydrazine Chemical compound NN OAKJQQAXSVQMHS-UHFFFAOYSA-N 0.000 description 92
- KGGVGTQEGGOZRN-PLNGDYQASA-N (nz)-n-butylidenehydroxylamine Chemical compound CCC\C=N/O KGGVGTQEGGOZRN-PLNGDYQASA-N 0.000 description 36
- 238000012360 testing method Methods 0.000 description 35
- IOVCWXUNBOPUCH-UHFFFAOYSA-N Nitrous acid Chemical compound ON=O IOVCWXUNBOPUCH-UHFFFAOYSA-N 0.000 description 28
- 238000009826 distribution Methods 0.000 description 21
- GKLVYJBZJHMRIY-UHFFFAOYSA-N technetium atom Chemical compound [Tc] GKLVYJBZJHMRIY-UHFFFAOYSA-N 0.000 description 17
- 229910052713 technetium Inorganic materials 0.000 description 16
- 230000006378 damage Effects 0.000 description 15
- 238000006243 chemical reaction Methods 0.000 description 14
- 239000012071 phase Substances 0.000 description 14
- IYQHAABWBDVIEE-UHFFFAOYSA-N [Pu+4] Chemical compound [Pu+4] IYQHAABWBDVIEE-UHFFFAOYSA-N 0.000 description 9
- 238000005192 partition Methods 0.000 description 9
- 239000002915 spent fuel radioactive waste Substances 0.000 description 9
- 238000000638 solvent extraction Methods 0.000 description 8
- 229910052768 actinide Inorganic materials 0.000 description 7
- 150000001255 actinides Chemical class 0.000 description 7
- 238000010586 diagram Methods 0.000 description 7
- 239000000243 solution Substances 0.000 description 7
- 238000003756 stirring Methods 0.000 description 7
- 239000000126 substance Substances 0.000 description 7
- AAORDHMTTHGXCV-UHFFFAOYSA-N uranium(6+) Chemical compound [U+6] AAORDHMTTHGXCV-UHFFFAOYSA-N 0.000 description 7
- 238000004364 calculation method Methods 0.000 description 6
- 238000005202 decontamination Methods 0.000 description 6
- 230000003588 decontaminative effect Effects 0.000 description 6
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 description 6
- 238000010405 reoxidation reaction Methods 0.000 description 6
- 229910052781 Neptunium Inorganic materials 0.000 description 5
- 238000000658 coextraction Methods 0.000 description 5
- 238000004090 dissolution Methods 0.000 description 5
- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 description 5
- 230000009467 reduction Effects 0.000 description 5
- 239000002253 acid Substances 0.000 description 4
- 239000007864 aqueous solution Substances 0.000 description 4
- 238000005119 centrifugation Methods 0.000 description 4
- 150000001875 compounds Chemical class 0.000 description 4
- 229940094933 n-dodecane Drugs 0.000 description 4
- 238000002798 spectrophotometry method Methods 0.000 description 4
- 230000033228 biological regulation Effects 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- 230000006641 stabilisation Effects 0.000 description 3
- 238000011105 stabilization Methods 0.000 description 3
- FZENGILVLUJGJX-IHWYPQMZSA-N (Z)-acetaldehyde oxime Chemical compound C\C=N/O FZENGILVLUJGJX-IHWYPQMZSA-N 0.000 description 2
- BNYNJIKGRPHFAM-BQYQJAHWSA-N (ne)-n-heptylidenehydroxylamine Chemical compound CCCCCC\C=N\O BNYNJIKGRPHFAM-BQYQJAHWSA-N 0.000 description 2
- 108050001922 30S ribosomal protein S17 Proteins 0.000 description 2
- 101000812304 Bacillus subtilis (strain 168) 30S ribosomal protein S16 Proteins 0.000 description 2
- 101000675258 Geobacillus stearothermophilus 30S ribosomal protein S19 Proteins 0.000 description 2
- 229910002651 NO3 Inorganic materials 0.000 description 2
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 2
- 230000009471 action Effects 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 2
- 230000002051 biphasic effect Effects 0.000 description 2
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000004817 gas chromatography Methods 0.000 description 2
- 238000004128 high performance liquid chromatography Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- SQDFHQJTAWCFIB-UHFFFAOYSA-N n-methylidenehydroxylamine Chemical compound ON=C SQDFHQJTAWCFIB-UHFFFAOYSA-N 0.000 description 2
- 230000003071 parasitic effect Effects 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 239000002904 solvent Substances 0.000 description 2
- 238000004611 spectroscopical analysis Methods 0.000 description 2
- 230000000087 stabilizing effect Effects 0.000 description 2
- 238000005406 washing Methods 0.000 description 2
- -1 π-dodecane or TPH Chemical compound 0.000 description 2
- GGZXEEFQIXMFBF-CMDGGOBGSA-N (ne)-n-octylidenehydroxylamine Chemical compound CCCCCCC\C=N\O GGZXEEFQIXMFBF-CMDGGOBGSA-N 0.000 description 1
- YUKIAUPQUWVLBK-WAYWQWQTSA-N (nz)-n-pentylidenehydroxylamine Chemical compound CCCC\C=N/O YUKIAUPQUWVLBK-WAYWQWQTSA-N 0.000 description 1
- BZJTUOGZUKFLQT-UHFFFAOYSA-N 1,3,5,7-tetramethylcyclooctane Chemical group CC1CC(C)CC(C)CC(C)C1 BZJTUOGZUKFLQT-UHFFFAOYSA-N 0.000 description 1
- DMJZWFZICOEEAJ-UHFFFAOYSA-N 2-(4-bromothiophen-3-yl)sulfanylpropanoic acid Chemical compound OC(=O)C(C)SC1=CSC=C1Br DMJZWFZICOEEAJ-UHFFFAOYSA-N 0.000 description 1
- 101150077457 ACOX1 gene Proteins 0.000 description 1
- 229910052695 Americium Inorganic materials 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical group [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 229910052685 Curium Inorganic materials 0.000 description 1
- KJTLSVCANCCWHF-UHFFFAOYSA-N Ruthenium Chemical compound [Ru] KJTLSVCANCCWHF-UHFFFAOYSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- FLDCUAAEHVCAMQ-UHFFFAOYSA-N [Pu+2] Chemical compound [Pu+2] FLDCUAAEHVCAMQ-UHFFFAOYSA-N 0.000 description 1
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 description 1
- RAESLDWEUUSRLO-UHFFFAOYSA-O aminoazanium;nitrate Chemical group [NH3+]N.[O-][N+]([O-])=O RAESLDWEUUSRLO-UHFFFAOYSA-O 0.000 description 1
- 239000003963 antioxidant agent Substances 0.000 description 1
- 238000013475 authorization Methods 0.000 description 1
- 230000000711 cancerogenic effect Effects 0.000 description 1
- 231100000315 carcinogenic Toxicity 0.000 description 1
- 239000013626 chemical specie Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 150000007857 hydrazones Chemical class 0.000 description 1
- 150000002430 hydrocarbons Chemical group 0.000 description 1
- NILJXUMQIIUAFY-UHFFFAOYSA-N hydroxylamine;nitric acid Chemical compound ON.O[N+]([O-])=O NILJXUMQIIUAFY-UHFFFAOYSA-N 0.000 description 1
- 239000003350 kerosene Substances 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 231100000219 mutagenic Toxicity 0.000 description 1
- 230000003505 mutagenic effect Effects 0.000 description 1
- WIXWMTMSISERBV-UHFFFAOYSA-N n-nonylidenehydroxylamine Chemical compound CCCCCCCCC=NO WIXWMTMSISERBV-UHFFFAOYSA-N 0.000 description 1
- GGZXEEFQIXMFBF-UHFFFAOYSA-N n-octylidenehydroxylamine Chemical compound CCCCCCCC=NO GGZXEEFQIXMFBF-UHFFFAOYSA-N 0.000 description 1
- 230000003472 neutralizing effect Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 229910052707 ruthenium Inorganic materials 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 238000004513 sizing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 231100000331 toxic Toxicity 0.000 description 1
- 230000002588 toxic effect Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 238000005303 weighing Methods 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
Classifications
-
- 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
-
- 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
-
- 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
Definitions
- the invention relates to the field of the treatment of spent nuclear fuels.
- the invention relates to the use of aldoximes comprising at least five carbon atoms as anti-nitrous agents in reductive plutonium de-extraction operations.
- the invention is applicable to all spent nuclear fuel treatment processes that include one or more plutonium reducing desuperation operations.
- Such operations are particularly present in the PUREX process as it is implemented in modern spent nuclear fuel treatment plants (that is to say the UP3 and UP2-800 plants of La Hague in France and Rokkasho plant in Japan), firstly to carry out the U / Pu partitioning step of the first decontamination cycle of this process and, secondly, to complete the decontamination of plutonium into fission products in the process.
- plutonium purification cycle conventionally called “plutonium second cycle", which follows this first cycle of decontamination.
- the plutonium reducing desextraction operations which are carried out in the above-mentioned processes for the treatment of spent nuclear fuel, consist of passing the plutonium from an organic phase (or solvent phase), in which it is at the stage of oxidation (IV), in an aqueous phase by reducing it to the oxidation state (III), a state in which its affinity for the organic phase is very low.
- plutonium (IV) to plutonium (III) is induced by a reducing agent which is added to the aqueous phase for desextraction and stabilized by an anti-nitrous agent.
- the Reducing agent used to extract the plutonium during the partition stage U / Pu is uranium (IV) (or uranous nitrate), while the anti-nitrous agent is hydrazinium nitrate, also called hydrazine.
- the first two reactions take place in the aqueous and organic phases whereas the reaction of destruction of nitrous acid by hydrazine takes place only in the aqueous phase because of the inextractability of hydrazine by the organic phase. , the latter being composed of 30% (v / v) tri-n-butyl phosphate (or TBP) in hydrogenated tetrapropylene (or TPH).
- TBP tri-n-butyl phosphate
- TPH hydrogenated tetrapropylene
- plutonium (III) in the organic phase, even in small quantities, catalyzes the oxidation of uranium (IV) through the first two reactions and thus generates nitrous acid.
- butanal oxime in combination with hydrazine, has a number of advantages, in particular in that it makes it possible to reduce the quantities of uranous nitrate and of hydrazine necessary for the realization of a reductive extraction of plutonium and thus lessen the drawbacks related to the non-extraction of hydrazine in the organic phase, but it is not totally satisfactory from made :
- hydrazine is part of the list of CMR substances, ie the substances which are considered by Regulation (EC) 1907/2006 on the registration, evaluation, authorization and chemical substances (REACH Regulation) as potentially or in a known way carcinogenic, mutagenic and / or toxic for reproduction, and is likely to be listed in the more or less long term in Annex XIV of this Regulation, in which case its placing on the market and its industrial use will be prohibited unless specifically granted by the European Chemicals Agency (ECHA).
- ECHA European Chemicals Agency
- the inventors have therefore set themselves the goal of finding compounds having a high anti-nitrous power but the use of which is free from the disadvantages presented by the use of hydrazine such as currently implemented in the PUREX process or by the use of a biphasic butanal oxime / hydrazine system as proposed in reference [3].
- the aldoxime corresponds to the above form in which R comprises at most 12 carbon atoms and, advantageously, at most 8 carbon atoms.
- the aldoxime corresponds to the above formula wherein R represents a linear alkyl chain comprising from 4 to 8 carbon atoms.
- pentanal oxime and hexanal oxime are particularly preferred.
- the process of reducing the extraction of plutonium preferably comprises:
- an organic phase immiscible with water, comprising an extractant and plutonium at the oxidation state IV in an organic diluent, with an aqueous phase comprising a reducing agent capable of reducing the plutonium ( IV) in plutonium (III) and nitric acid, the aldoxime being present either in the organic phase or in the aqueous phase according to its solubility in water;
- pentanal oxime which is partially soluble in water and partially soluble in organic diluents that may be used in plutonium-reducing reductive extraction operations (under the conditions of temperature and pressure conventionally used in these operations), may be added to the aqueous phase as well as to the organic phase while the aldoximes containing 6 or more carbon atoms, which are insoluble or almost insoluble in water (under the aforementioned conditions), are added to the organic phase.
- the reducing agent present in the aqueous phase is preferably chosen from uranium (IV), hydroxylammonium nitrate, also called hydroxylamine nitrate, alkylated hydroxylamine derivatives, Ferrous sulfamate and sulfamic acid.
- uranium (IV) and hydroxylammonium nitrate both of which are used to reduce plutonium (IV) to plutonium (III) in the PUREX process, are the most preferred.
- the extracting agent is preferably a tri-n-alkyl phosphate and, more preferably, TBP while the organic diluent is preferably a linear or branched dodecane such as ⁇ -dodecane or TPH, an isoparaffinic solvent such as Isane IP185, Isane IP165 or Isopar L, or kerosene, in which case the extracting agent is preferably present at 30% (v / v) in this organic diluent.
- aldoxime is used at a concentration ranging preferably from 0.01 mol / L to 3 mol / L and, more preferably, from 0.05 mol / L to 0.5 mol / L of organic or aqueous phase, while the reducing agent is used, preferably, at a concentration ranging from 0.2 mol / L to 0.6 mol / L and more preferably 0.2 mol / L at 0.4 mol / L of aqueous phase.
- the nitric acid it is advantageously present in the aqueous phase at a concentration ranging from 0.05 mol / l to 2 mol / l.
- aldoxime can be used as the sole anti-nitrous agent in the plutonium reductive desextraction operation if it is distributed in a balanced manner between the organic phase and the aqueous phase when they are brought into contact with each other. with each other.
- aldoxime is highly extractable by the organic phase (under the conditions of temperature and pressure conventionally used in plutonium reductive de-extraction operations), which will typically occur for aldoximes having 6 or more carbon atoms such as hexanal oxime, heptanal oxime or octanal oxime -, then this aldoxime is advantageously used in combination with a second anti-nitrous agent which is itself an oxime no extractable by this organic phase (under the same conditions of temperature and pressure).
- the plutonium reducing desextraction operation is preferably one of the PUREX process plutonium or COEX process extraction operations.
- the invention has many advantages. Indeed, it offers a range of anti-nitrous agents which are capable, for some when used alone and for others when used in combination with an oxime not extractable by an organic phase, to block very well. effectively the reoxidation of plutonium (III) to plutonium (IV) both in an organic phase and in an aqueous phase.
- the invention makes it possible to carry out reductive plutonium de-extraction operations without the use of hydrazine, whether this is an operation such as that which is carried out in the U / Pu partition of the PUREX process or of an operation such as that implemented in the second plutonium cycle of the same process, it also makes it possible to reduce very strongly the quantities of reducing agent and anti-nitride agent required. performing these operations with respect to the quantities required when the anti-nitrous agent is hydrazine.
- the invention also allows to consider a reduction in the sizing of equipment currently used to perform operations of reductive extraction of plutonium.
- Figure 1 shows the distribution coefficients of pentanal oxime (symbol ⁇ ) and hexanal oxime (symbol ⁇ ) between organic phases comprising TBP in n-dodecane and aqueous phases comprising different concentrations of nitric acid; for comparison, are also shown in this figure the distribution coefficients as obtained under the same conditions for butanal oxime (symbol A).
- Figures 2A and 2B show the distribution coefficients of pentanal oxime (symbol I) and hexanal oxime (symbol ⁇ ) between organic phases and aqueous phases simulating, in terms of uranium (VI) concentration and concentration of nitric acid, the organic phases and the aqueous phases which are obtained during the U / Pu partitioning step of the PUREX process.
- aqueous phases simulating, in terms of uranium (VI) concentration and concentration of nitric acid
- Figure 3 illustrates the kinetics of destruction of nitrous acid by pentanal oxime (curve A) in a nitric aqueous phase; for comparison, are also shown in this figure the kinetics of destruction of nitrous acid by butanal oxime (curve B) and acetaldoxime (curve C) as obtained under the same conditions.
- FIG. 4 illustrates the kinetics of destruction of nitrous acid by pentanal oxime (curve A) and hexanal oxime (curve B) in organic phases comprising TBP in n-dodecane; for comparison, is also shown in this figure the kinetics of destruction of nitrous acid by butanal oxime (curve C) as obtained under the same conditions.
- FIG. 5 illustrates the oxidation kinetics of uranium (IV) obtained in the presence of pentanal oxime (curve A) and hexanal oxime (curve B) in organic phases comprising TBP in ⁇ -dodecane, after setting in contact with these organic phases with a nitric aqueous phase and then separation of these phases; for comparison, are also represented in this figure oxidation kinetics of uranium (IV) as obtained, under the same conditions, in the presence of butanal oxime (curve C) and in the absence of any oxime (curve D).
- FIG. 6 illustrates the kinetics of oxidation of uranium (IV) obtained in the presence of pentanal oxime (curve A) in an aqueous nitric phase; for comparison, are also shown in this figure the oxidation kinetics of uranium (IV) as obtained, under the same conditions, in the presence of butanal oxime (curve B), acetaldoxime (curve C) and hydrazine (curve D).
- FIG. 7 illustrates the kinetics of oxidation of uranium (IV) present in an organic phase (TBP / TPH) resulting from a reductive plutonium desextraction test in which hexanal oxime has been used as an anti-nitrous agent .
- FIG. 8 illustrates the kinetics of oxidation of uranium (IV) present in an organic phase (TBP / TPH) resulting from a reductive plutonium desextraction test in which hexanal oxime has been used as an anti-nitrous agent. and wherein technetium was desextracted together with the plutonium.
- FIG. 9 illustrates the kinetics of oxidation of uranium (IV) in an organic phase (TBP / TPH) resulting from a reductive plutonium desextraction test in which pentanal oxime has been used as an anti-nitrous agent.
- Figure 10 illustrates the oxidation kinetics of uranium (IV) in the presence of acetaldoxime in aqueous nitric phases comprising 100 mg / L (symbol ⁇ ) or 200 mg / L (symbol x) of technetium; for comparison, are also represented in this figure oxidation kinetics of uranium (IV) as obtained, under the same conditions, in the presence of hydrazine and 100 mg / L (symbol ⁇ ) or 200 mg / L (symbol ⁇ ) of technetium.
- FIG. 11 illustrates a treatment scheme of a dissolution liquor of a spent nuclear fuel comprising a U / Pu partitioning step in which a hexanal oxime / acetaldoxime combination is used as an anti-nitrous system;
- the rectangles referenced 1 to 7 represent multi-stage extractors such as those conventionally used in the treatment of spent nuclear fuels (mixer-settlers, pulsed columns, centrifugal extractors);
- the organic phases entering and leaving the extractors are symbolized by solid lines, while the aqueous phases entering and leaving these extractors are symbolized by dashed lines.
- FIG. 12 illustrates the profile of the concentrations of uranium (IV) in the aqueous phases circulating in extractors 5 and 6 of the diagram illustrated in FIG. 11, as obtained by calculations (curve A); for comparison, are also the profile of the concentrations of uranium (IV) that would be obtained if hexanal oxime and acetaldoxime were replaced in this scheme by hydrazine (curve B) and the profile of uranium concentrations (IV ) that would be obtained if the plutonium (III) reoxidation reactions were completely neutralized (curve C).
- FIG. 13 illustrates the profiles of the concentrations of plutonium in the aqueous phases circulating in the extractors 5 and 6 of the diagram illustrated in FIG. 11, as obtained experimentally (symbol x) and by calculations (curve -).
- FIG. 14 illustrates the concentration profiles of uranium (IV), uranium (VI) and total uranium in the aqueous phases circulating in extractors 5 and 6 of the diagram illustrated in FIG. 11, such as 'obtained experimentally and by calculations; in this figure, the symbols x, ⁇ and ⁇ respectively correspond to the profiles of the concentrations of uranium (VI), uranium (IV) and total uranium obtained experimentally, whereas the curves A, B and C correspond respectively to the profiles of the concentrations of uranium (VI), uranium (IV) and total uranium obtained by calculations.
- the distribution coefficients, denoted D, of pentanal oxime and hexanal oxime were determined by two series of tests, namely:
- each organic phase was brought into contact, volume to volume, for 15 minutes, at room temperature (20-25 ° C.) and with stirring, with a nitric aqueous phase.
- Pentanal oxime was added to the aqueous phase while hexanal oxime was added to the organic phase, each at a concentration of 0.1 mol / L of phase.
- the distribution coefficients obtained in the second series of tests are presented in Table 2 below. They are also shown in FIGS. 2A and 2B in which the values of the distribution coefficients (in ordinate) and the acidity of the aqueous phases (in abscissa) have been transposed and in which the distribution coefficients of the pentanal oxime correspond to the symbol ⁇ while the distribution coefficients hexanal oxime correspond to the symbol ⁇ .
- the ordinates are at a decimal scale in Figure 2A and at a log scale in Figure 2B.
- pentanal oxime and hexanal oxime have much higher distribution coefficients than butanal oxime, which means that they are much more extractable in the organic phase than the latter.
- the distribution coefficients of pentanal oxime and hexanal oxime are decreased compared to what they are in the absence of actinides; however, they remain high enough that pentanal oxime and hexanal oxime are still significantly extracted. Under the same conditions, the distribution coefficients of butanal oxime are less than 1.
- the distribution coefficients of pentanal oxime and hexanal oxime allow:
- pentanal oxime a balanced distribution between organic phase and aqueous phase, hence the possibility of developing reductive plutonium desextraction schemes in which pentanal oxime would be used alone to stabilize both the organic phase and the aqueous phase; while
- hexanal oxime a quasi-quantitative extraction in the organic phase, hence the possibility of developing reductive plutonium desextraction schemes in which hexanal oxime would be used, in very small quantities, to stabilize the organic phase, the phase aqueous can then be stabilized by a hydrophilic oxime such as acetaldoxime; and
- the initial concentrations of nitrous acid and pentanal oxime or butanal oxime in the nitric aqueous phases were 0.005 mol / L and 0.025 mol / L, respectively.
- FIGS. 3 and 4 The results of these tests are illustrated in FIGS. 3 and 4 in the form of curves expressing the percentage of residual nitrous acid as a function of time (in seconds in FIG. 3 and in minutes in FIG. 4).
- curve A corresponds to the results obtained for pentanal oxime while curve B corresponds to the results obtained for butanal oxime.
- curve C the kinetics of destruction of nitrous acid by acetaldoxime
- curve A corresponds to the results obtained for pentanal oxime
- curve B corresponds to the results obtained for hexanal oxime
- curve C corresponds to the results obtained for butanal oxime.
- pentanal oxime although containing a number of carbon atoms greater than that of butanal oxime and acetaldoxime, has an anti-nitrous action equivalent to that of butanal oxime and acetaldoxime ( Figure 3); while
- the initial concentrations of uranium (IV) and the anti-nitrous agent (oxime or hydrazine) in the nitric aqueous phases were 66 g / L and 0.2 mol / L.
- FIGS. 5 and 6 The results of these tests are illustrated in FIGS. 5 and 6 in the form of curves expressing the percentage of residual uranium (IV) as a function of time (in hours in FIG. 5 and in days in FIG. 6).
- curve A corresponds to the results obtained for pentanal oxime
- curve B corresponds to the results obtained for hexanal oxime
- curve C corresponds to the results obtained for butanal oxime
- curve D corresponds to the results obtained in the absence of oxime.
- curve A corresponds to the results obtained for pentanal oxime
- curve B corresponds to the results obtained for butanal oxime
- curve C corresponds to the results obtained for acetaldoxime
- curve D corresponds to the results obtained for hydrazine.
- the uranium (IV) is perfectly stable in the organic phase for at least 15 hours in the presence of an oxime while its oxidation is complete in less than 8 hours in the absence of any oxime.
- the ability of pentanal oxime and hexanal oxime to stabilize uranium (IV) in the organic phase is greater than that of butanal oxime since less than 10% of uranium (IV) are oxidized in 100 hours in the presence of pentanal oxime and hexanal oxime, which is not the case in the presence of butanal oxime.
- BX1 to BX10 The anti-nitrous potency of pentanal oxime and hexanal oxime has been evaluated in a series of tests, hereinafter referred to as BX1 to BX10, representative of the chemical conditions in which a plutonium-reducing reductive operation is carried out.
- BX1 to BX10 representative of the chemical conditions in which a plutonium-reducing reductive operation is carried out.
- nitric acid 1 mol / L or 2 mol / L solutions of nitric acid, including uranium (VI), uranium (IV) (as a reducing agent for plutonium (IV) ) and, optionally, hydrazine and technetium, at the concentrations indicated in Tables 3 and 4 below; and
- solutions of TBP at 30% (v / v) in TPH comprising an oxime, uranium (VI) and plutonium (IV) at the concentrations indicated in tables 3 and 4 below .
- Oximes were introduced into the organic phases in solid form (the quantity of oxime introduced being controlled by weighing).
- the organic phases and the aqueous phases were brought into contact for 15 minutes (except in the case of the BX3 test for which the contact time was only 5 minutes), at room temperature (20-25 ° C. ) and with stirring, in a volume ratio O / A of 2, then these phases were separated from each other.
- the concentrations of uranium (VI), uranium (IV) and plutonium (III) in the aqueous phases were measured by UV-visible spectrophotometry and total plutonium by alpha spectrometry.
- the concentrations of uranium (VI) and uranium (IV) in the organic phases were measured by UV-visible spectrophotometry and that of the total plutonium by alpha spectrometry.
- Table 3 corresponding to the results obtained for the tests having been carried out with hexanal oxime (BX1 to BX5, BX8 and BX10) and Table 4 corresponding to results obtained for the tests carried out with pentanal oxime (BX6 and BX7).
- Table 3 corresponding to the results obtained for the tests having been carried out with hexanal oxime (BX1 to BX5, BX8 and BX10) and Table 4 corresponding to results obtained for the tests carried out with pentanal oxime (BX6 and BX7).
- pentanal oxime also makes it possible to limit the redox phenomena leading to an additional consumption of uranium (IV), with performances slightly lower than those obtained with hexanal oxime since the ratio U (IV) C ons. / pudes. obtained with pentanal oxime is between 0.6 and 0.8 (tests BX8 and BX10).
- FIGS. 7, 8 and 9 which respectively correspond to the organic phases BX5, BX10 and BX6.
- a treatment scheme for a dissolution liquor of a spent nuclear fuel comprising a U / Pu partitioning step which is carried out without hydrazine but in which a hexanal oxime / acetaldoxime combination is used as an anti-nitrous system - hexanal oxime being used in organic phase and acetaldoxime being used in aqueous phase - was developed.
- acetaldoxime is really capable of replacing hydrazine as an anti-nitrous agent in the aqueous phase, in the presence of technetium;
- hexanal oxime is also capable of stabilizing uranium (IV) in the organic phase used to carry out the so-called "Np wash" operation which, in the PUREX and COEX processes, serves to eliminate, of the aqueous phase resulting from the plutonium reducing desextraction operation, the neptunium having been desextracted during this operation.
- Tests have been carried out to compare the anti-nitrous power in the aqueous phase of acetaldoxime with that of hydrazine and this in the presence of technetium.
- aqueous solutions comprising 9 g / l of uranium (IV) and 2 mol / l of nitric acid and 0.2 mol / l of acetaldoxime or of hydrazine, these solutions being thermostatically controlled at 35 ° C .;
- VII technetium
- the anti-nitrous power of acetaldehyde oxime is, in the aqueous phase and in the presence of 100 mg or 200 mg of technetium, comparable to that of hydrazine.
- TBP solutions at 30% (v / v) in TPH optionally comprising 0.1 mol / L of hexanal oxime;
- the organic phases and aqueous phases were brought into contact, volume-to-volume, for 15 minutes, at room temperature (20-25 ° C.) and with stirring, and then these phases were separated from each other.
- PF washing an operation, called "PF washing” in FIG. 11, which aims at removing from the organic phase resulting from the "Co-extraction U / Pu” operation fission products and, in particular, ruthenium and zirconium, having been extracted during the "Co-extraction U / Pu";
- Te wash an operation, called "Te wash” in Figure 11, which aims to remove the organic phase from the "PF wash” technetium was extracted during the "Co-extraction U / Pu" by means of a aqueous phase ; as well as'
- washing Np an operation, called "washing Np" in Figure 11, which aims to remove from the aqueous phase resulting from the "Pu / U Desextraction” the uranium in excess with respect to the U / Pu mass ratio target of 20/80 to 30/70, and the fraction of neptunium that followed the plutonium in the aqueous phase at course of "Pu / U Desextraction”;
- hydrazine which is the anti-nitrous agent used in the COEX process, is replaced by a hexanal oxime / acetaldoxime combination.
- the hexanal oxime (denoted HexOx in FIG. 11) is introduced, given its highly lipophilic nature, into the organic phase entering the extractor 5 in which the "Np wash” takes place. as well as in the organic phase resulting from “Washing Te" just before it enters the extractor 6.
- Acetaldoxime (denoted AcOx in FIG. 11) is itself introduced, given its hydrophilic nature, into the aqueous phase circulating in the extractor 6, this introduction being carried out on three different stages of this extractor: stage 8 at which it is injected into the aqueous phase for desextraction and stages 1 and 4 at which the acetaldoxime is injected into the aqueous streams used to supply this aqueous phase uranium (IV).
- These models have been implemented in the PAREX code which is a software for simulating the sharing of species of interest in operations such as those of partitioning uranium and plutonium into two aqueous streams. It is on the basis of this simulation that the operating parameters were determined in which the diagram illustrated in FIG. 11 was tested experimentally.
- Figure 12 compares the concentration profiles of uranium (IV) in the aqueous phases circulating in the extractors 5 and 6 as calculated for, on the one hand, the diagram illustrated in FIG. 11 (curve A) and, on the other hand, for a homologous scheme using hydrazine (curve B) .
- the ideal profile obtained by neutralizing (in the PAREX code) the reoxidation reactions of plutonium (II) is also shown (curve C).
- FIG. 11 The diagram illustrated in FIG. 11 has been successfully implemented, in the ATALANTE process shielded cell, on a real solution of a spent nuclear fuel.
- This scheme made it possible to produce a plutonium stream with a concentration of 10 g / L with a consequent concentration of uranium (IV) (16 g / L), and this, without any additional uranium (IV) in the operation.
- Uranium (IV) consumption is also lower than in the hydrazine regimen.
- FIG. 13 illustrates the profiles of the plutonium concentrations in the aqueous phases circulating in the extractors 5 and 6, as obtained experimentally (symbol x) and as calculated by the PAREX code (curve-), while FIG. 14 illustrates the concentration profiles of uranium (IV), uranium (VI) and total uranium of the aqueous phases circulating in these same extractors, as obtained experimentally and by calculations; in this figure, the symbols x, ⁇ and ⁇ respectively correspond to the profiles of the concentrations of uranium (IV), uranium (VI) and total uranium obtained experimentally, as well as the curves A, B and C correspond respectively to the profiles of the concentrations of uranium (IV), uranium (VI) and total uranium obtained by calculations.
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FR1560048A FR3042904B1 (fr) | 2015-10-21 | 2015-10-21 | Utilisation d'aldoximes comprenant au moins cinq atomes de carbone comme agents anti-nitreux dans des operations de desextraction reductrice du plutonium |
PCT/EP2016/074987 WO2017067933A1 (fr) | 2015-10-21 | 2016-10-18 | Utilisation d'aldoximes comprenant au moins cinq atomes de carbone comme agents anti-nitreux dans des opérations de désextraction réductrice du plutonium |
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JP (1) | JP6876688B2 (fr) |
CN (1) | CN108369828B (fr) |
FR (1) | FR3042904B1 (fr) |
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EP1105883A1 (fr) * | 1998-08-28 | 2001-06-13 | British Nuclear Fuels PLC | Retraitement de combustible nucleaire avec reduction de np(vi) en np(v) a l'aide d'une oxime |
RU2229178C2 (ru) * | 1998-08-28 | 2004-05-20 | Бритиш Нуклеа Фюэлс ПЛС | Способ переработки отработанного ядерного топлива (варианты), восстановитель np(vi) |
FR2862804B1 (fr) * | 2003-11-20 | 2006-01-13 | Commissariat Energie Atomique | Procede de separation de l'uranium (vi) d'actinides (iv) et/ou (vi)et ses utilisations |
FR2880180B1 (fr) * | 2004-12-29 | 2007-03-02 | Cogema | Perfectionnement du procede purex et ses utilisations |
FR2900159B1 (fr) * | 2006-04-19 | 2008-06-13 | Commissariat Energie Atomique | Separation groupee des actinides a partir d'une phase aqueuse fortement acide |
FR2907346B1 (fr) * | 2006-10-23 | 2009-01-30 | Commissariat Energie Atomique | Separation groupee des actinides a partir d'une phase aqueuse fortement acide, utilisant un extractant solvatant en milieu relargant. |
FR2917227A1 (fr) * | 2007-06-07 | 2008-12-12 | Commissariat Energie Atomique | Utilisation de l'oxime de butyraldehyde en tant qu'agent anti-nitreux dans le retraitement de combustibles nucleaires uses. |
FR2947663B1 (fr) | 2009-07-02 | 2011-07-29 | Areva Nc | Procede ameliore de traitement de combustibles nucleaires uses |
CN103451455B (zh) * | 2012-05-28 | 2015-01-07 | 中国原子能科学研究院 | Purex流程中铀、钚分离工艺 |
CN103325431B (zh) * | 2013-06-21 | 2016-01-27 | 中国原子能科学研究院 | 一种分离锝的purex流程 |
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WO2017067933A1 (fr) | 2017-04-27 |
RU2018118245A (ru) | 2019-11-21 |
CN108369828A (zh) | 2018-08-03 |
EP3365897B1 (fr) | 2019-11-06 |
JP6876688B2 (ja) | 2021-05-26 |
JP2018536847A (ja) | 2018-12-13 |
RU2718437C2 (ru) | 2020-04-06 |
FR3042904A1 (fr) | 2017-04-28 |
RU2018118245A3 (fr) | 2020-02-17 |
FR3042904B1 (fr) | 2017-12-15 |
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