CN105931692A - Method for stabilizing U(IV) valence state in TBP - Google Patents
Method for stabilizing U(IV) valence state in TBP Download PDFInfo
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- CN105931692A CN105931692A CN201610244630.2A CN201610244630A CN105931692A CN 105931692 A CN105931692 A CN 105931692A CN 201610244630 A CN201610244630 A CN 201610244630A CN 105931692 A CN105931692 A CN 105931692A
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- tbp
- aldoxime
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- organic facies
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- 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
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
- G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Extraction Or Liquid Replacement (AREA)
Abstract
The invention belongs to the technical field of after treatment of nuclear fuels, and discloses a method for stabilizing a U(IV) valence state in TBP. The method is implemented by introducing acetaldoxime into an organic phase of TBP; or introducing the acetaldoxime into a water phase, and then extracting the acetaldoxime into the organic phase of the TBP by a way of extraction, wherein the concentration of the acetaldoxime introduced into the organic phase of the TBP is 2-100mmol/L, and the concentration of the acetaldoxime introduced into the water phase is 20-1000mmol/L. The method has the advantages of being simple, and being capable of enabling the stabilization time of the U(IV) valence state in the TBP to be long.
Description
Technical field
The invention belongs to nuclear fuel reprocessing technical field, be specifically related to one and stablize U in TBP (IV) valence state
Method.
Background technology
In post processing Purex flow, generally using U (IV) is the Pu (IV) that reducing agent will easily be extracted by TBP
Revert to the Pu (III) of difficult extraction, but U (IV) can be gradually by the nitric acid in feed liquid and nitrite-oxidizing one-tenth
U (VI), wherein the Oxidation of nitrous acid is especially apparent, and this can accelerate mainly due to nitrous acid in self-catalysis
The oxidation of U (IV).U (IV) is oxidized to U (VI) can cause the increase of U (IV) amount of reagent, simultaneously U (IV)
The increase of usage amount also can reduce in plutonium except the effect of uranium.In order to solve this problem, traditional way is to use
Hydrazine removes nitrous acid as holding reductant, with stable U (IV) valence state, but there is problems in that U (IV) can
Partial extraction is in TBP, and nitrous acid relatively U (IV) is easily extracted in TBP, but hydrazine is difficult to be extracted by TBP,
Therefore hydrazine is as U (IV) valence state can only stablized during holding reductant in aqueous phase, and the U (IV) in organic facies is easy
Be extracted in TBP is nitrite-oxidizing.
In presently disclosed document, also not about how stablizing the report of U (IV) valence state in TBP extractant,
Therefore, it is badly in need of a kind of method solving this problem.
Summary of the invention
(1) goal of the invention
According to the problem existing for prior art, the invention provides a kind of method and simply and can make in TBP
The method of U (IV) valence stability time length.
(2) technical scheme
In order to solve the problem existing for prior art, the technical scheme that the present invention provides is as follows:
A kind of method stablizing U in TBP (IV) valence state, the method belongs to nuclear fuel reprocessing technical field, closes
Key is, the method is introducing aldoxime in TBP organic facies;Or in aqueous phase, introduce aldoxime, then
By the way of extraction, aldoxime is extracted in TBP organic facies;
The concentration of the aldoxime wherein introduced in TBP organic facies is 2~100mmol/L;Introduce in aqueous phase
The concentration of aldoxime be 20~1000mmol/L.
Preferably, the method is introducing aldoxime in TBP organic facies, and wherein the concentration of aldoxime is
2~100mmol/L.
Preferably, the method is carried out under the conditions of 5~40 DEG C.
(3) beneficial effect
The method of U (IV) valence stability in TBP in the post processing flow process that the present invention provides, the method by
In TBP organic facies introduce aldoxime or in aqueous phase introduce aldoxime reach remove nitrous acid purpose.Pass through
Measure the absorption photometric value of U (IV), learn that the method can make U (IV) the valence stability time reach more than 5 hours.
Its principle is:
In nitric acid medium, under 20 DEG C of temperature conditionss as a example by, the reaction rate constant of aldoxime and nitrous acid
For k=(921.6 ± 7.4) (mol/L)-1 . 5·min-1;And aldoxime can extract in organic facies TBP on a small quantity, if directly
Being added by aldoxime in organic facies, aldoxime also has certain dissolubility in TBP, with nitrous acid in organic facies
Reaction.
Accompanying drawing explanation
Fig. 1 be without aldoxime in the presence of, in TBP extractant, U (IV) absorbance changes over figure;
Fig. 2 is under aldoxime existence condition, and in TBP extractant, U (IV) absorbance changes over figure.
Detailed description of the invention
Below in conjunction with Figure of description and specific embodiment, the present invention is further elaborated.
Embodiment 1
With two parts of TBP-xylene solutions containing TBP volume fraction 10% by comparing 1:1 respectively abstraction purification after
U (IV) solution (uranium total concentration 3.09g/L, wherein U (IV) concentration 3.07g/L, purity >=99.2%, nitric acid
Concentration is 1mol/L), it is divided into two groups, and all under the conditions of 25 DEG C, the aqueous phase of one of which adds concentration
For the aldoxime of 20mmol/L, another group aqueous phase does not contains aldoxime.Organic facies, Mei Geyi is taken out after extraction
Mensuration of fixing time organic facies, at 450~700nm interval absorbances, can pass through the U (IV) feature in this region
Absworption peak investigates the valence stability of U (IV).
Experimental result as shown in Figure 1, 2, from result above, when depositing without aldoxime, after 2 hours, has
The peak value of machine middle U (IV) mutually has occurred substantially reducing, i.e. U (IV) there occurs oxidation;And in the presence of aldoxime,
Through 5 hours, the peak value of U (IV) was the most more stable.Can significantly improve organic so adding aldoxime in Shi Yan
The stability of mutually middle U (IV).
Water In The Experiment phase aldoxime concentration is the lowest, only 20mmol/L, and the aldoxime being extracted into organic facies is less,
As improved organic facies aldoxime concentration, the stabilization time of U (IV) valence state, therefore aldoxime was applicable to surely by longer
Determine the valence state of U in TBP (IV).
Embodiment 2
As different from Example 1, in addition aldoxime to organic facies, concentration is 2mmol/L.This embodiment
Temperature conditions be 40 DEG C.
Embodiment 3
As different from Example 1, in addition aldoxime to organic facies, concentration is 50mmol/L.This embodiment
Temperature conditions be 5 DEG C.
Embodiment 4
As different from Example 1, in addition aldoxime to organic facies, concentration is 100mmol/L.
Embodiment 5
As different from Example 1, in addition aldoxime to aqueous phase, concentration is 100mmol/L.
Embodiment 6
As different from Example 1, in addition aldoxime to aqueous phase, concentration is 500mmol/L.
Embodiment 7
As different from Example 1, in addition aldoxime to aqueous phase, concentration is 1000mmol/L.
Claims (3)
1. the method stablizing U in TBP (IV) valence state, it is characterised in that the method is located after belonging to nuclear fuel
Reason technical field, the method is introducing aldoxime in TBP organic facies;Or in aqueous phase, introduce aldoxime,
By the way of extraction, aldoxime is extracted in TBP organic facies again;
The concentration of the aldoxime wherein introduced in TBP organic facies is 2~100mmol/L;Introduce in aqueous phase
The concentration of aldoxime be 20~1000mmol/L.
One the most according to claim 1 stablizes the method for U in TBP (IV) valence state, it is characterised in that
The method is introducing aldoxime in TBP organic facies, and wherein the concentration of aldoxime is 2~100mmol/L.
One the most according to claim 1 stablizes the method for U in TBP (IV) valence state, it is characterised in that
The method is carried out under the conditions of 5~40 DEG C.
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Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6413482B1 (en) * | 1998-08-28 | 2002-07-02 | British Nuclear Fuels Plc | Method for reprocessing nuclear fuel by employing oximes |
CN101765890A (en) * | 2007-06-07 | 2010-06-30 | 法国原子能委员会 | Use of butyraldehyde oxime as anti-nitrous agent in an operation for the reducing back-extraction of plutonium |
CN102352436A (en) * | 2011-07-21 | 2012-02-15 | 中国原子能科学研究院 | Method for separating U (uranium) from Pu (plutonium) in Purex process |
CN103820656A (en) * | 2014-01-28 | 2014-05-28 | 中国原子能科学研究院 | Uranium and plutonium separation technology in Purex process |
-
2016
- 2016-04-19 CN CN201610244630.2A patent/CN105931692A/en active Pending
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6413482B1 (en) * | 1998-08-28 | 2002-07-02 | British Nuclear Fuels Plc | Method for reprocessing nuclear fuel by employing oximes |
CN101765890A (en) * | 2007-06-07 | 2010-06-30 | 法国原子能委员会 | Use of butyraldehyde oxime as anti-nitrous agent in an operation for the reducing back-extraction of plutonium |
CN102352436A (en) * | 2011-07-21 | 2012-02-15 | 中国原子能科学研究院 | Method for separating U (uranium) from Pu (plutonium) in Purex process |
CN103820656A (en) * | 2014-01-28 | 2014-05-28 | 中国原子能科学研究院 | Uranium and plutonium separation technology in Purex process |
Non-Patent Citations (2)
Title |
---|
叶国安: "Purex流程中有机无盐试剂的应用分析", 《原子能科学技术》 * |
韩清珍 等: "乙醛肟还原钚的动力学及其在Purex流程铀钚分离中的应用", 《原子能科学技术》 * |
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