CN113753956B - Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof - Google Patents
Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof Download PDFInfo
- Publication number
- CN113753956B CN113753956B CN202111028388.2A CN202111028388A CN113753956B CN 113753956 B CN113753956 B CN 113753956B CN 202111028388 A CN202111028388 A CN 202111028388A CN 113753956 B CN113753956 B CN 113753956B
- Authority
- CN
- China
- Prior art keywords
- uranium
- thorium
- mixed
- thermal decomposition
- particles
- 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.)
- Active
Links
- 239000002245 particle Substances 0.000 title claims abstract description 241
- GFRMDONOCHESDE-UHFFFAOYSA-N [Th].[U] Chemical compound [Th].[U] GFRMDONOCHESDE-UHFFFAOYSA-N 0.000 title claims abstract description 131
- 238000002360 preparation method Methods 0.000 title abstract description 54
- 239000000443 aerosol Substances 0.000 claims abstract description 74
- 238000005979 thermal decomposition reaction Methods 0.000 claims abstract description 64
- 239000007788 liquid Substances 0.000 claims abstract description 45
- 238000000034 method Methods 0.000 claims abstract description 44
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 42
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 42
- 239000012159 carrier gas Substances 0.000 claims abstract description 40
- 239000007789 gas Substances 0.000 claims abstract description 37
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 claims abstract description 34
- 229910052776 Thorium Inorganic materials 0.000 claims abstract description 34
- 239000011259 mixed solution Substances 0.000 claims abstract description 30
- 150000001875 compounds Chemical class 0.000 claims abstract description 16
- 230000008569 process Effects 0.000 claims abstract description 15
- 239000002904 solvent Substances 0.000 claims abstract description 14
- 230000009471 action Effects 0.000 claims abstract description 11
- 238000002156 mixing Methods 0.000 claims abstract description 6
- 238000001816 cooling Methods 0.000 claims description 51
- KFZMGEQAYNKOFK-UHFFFAOYSA-N Isopropanol Chemical compound CC(C)O KFZMGEQAYNKOFK-UHFFFAOYSA-N 0.000 claims description 24
- 239000000498 cooling water Substances 0.000 claims description 22
- 239000011859 microparticle Substances 0.000 claims description 12
- VGBPIHVLVSGJGR-UHFFFAOYSA-N thorium(4+);tetranitrate Chemical compound [Th+4].[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O VGBPIHVLVSGJGR-UHFFFAOYSA-N 0.000 claims description 12
- 229910002007 uranyl nitrate Inorganic materials 0.000 claims description 12
- 239000012528 membrane Substances 0.000 claims description 8
- 238000004062 sedimentation Methods 0.000 claims description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- CSCPPACGZOOCGX-UHFFFAOYSA-N Acetone Chemical compound CC(C)=O CSCPPACGZOOCGX-UHFFFAOYSA-N 0.000 claims description 6
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 claims description 6
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 5
- 238000001914 filtration Methods 0.000 claims description 4
- 239000000463 material Substances 0.000 claims description 4
- 239000010453 quartz Substances 0.000 claims description 4
- 238000004891 communication Methods 0.000 claims description 3
- 239000002826 coolant Substances 0.000 claims description 3
- RUJLHPZAKCVICY-UHFFFAOYSA-J thorium(4+);disulfate Chemical compound [Th+4].[O-]S([O-])(=O)=O.[O-]S([O-])(=O)=O RUJLHPZAKCVICY-UHFFFAOYSA-J 0.000 claims description 3
- 229910000384 uranyl sulfate Inorganic materials 0.000 claims description 3
- 238000009826 distribution Methods 0.000 abstract description 21
- 238000011084 recovery Methods 0.000 abstract description 18
- 239000000203 mixture Substances 0.000 abstract description 9
- 239000012798 spherical particle Substances 0.000 abstract description 4
- 239000000243 solution Substances 0.000 description 18
- 239000000843 powder Substances 0.000 description 11
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 9
- 238000010438 heat treatment Methods 0.000 description 9
- 229910000439 uranium oxide Inorganic materials 0.000 description 9
- 238000004458 analytical method Methods 0.000 description 7
- 238000001514 detection method Methods 0.000 description 7
- 230000000052 comparative effect Effects 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 6
- 238000001095 inductively coupled plasma mass spectrometry Methods 0.000 description 6
- 238000004519 manufacturing process Methods 0.000 description 6
- 238000010586 diagram Methods 0.000 description 5
- 238000007865 diluting Methods 0.000 description 5
- 239000010419 fine particle Substances 0.000 description 5
- 238000005259 measurement Methods 0.000 description 5
- 238000000550 scanning electron microscopy energy dispersive X-ray spectroscopy Methods 0.000 description 5
- 239000011824 nuclear material Substances 0.000 description 4
- 238000005204 segregation Methods 0.000 description 4
- 238000012876 topography Methods 0.000 description 4
- 238000005303 weighing Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 238000001000 micrograph Methods 0.000 description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 3
- WJWSFWHDKPKKES-UHFFFAOYSA-N plutonium uranium Chemical compound [U].[Pu] WJWSFWHDKPKKES-UHFFFAOYSA-N 0.000 description 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 2
- 238000005054 agglomeration Methods 0.000 description 2
- 230000002776 aggregation Effects 0.000 description 2
- 230000003321 amplification Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 238000004807 desolvation Methods 0.000 description 2
- 230000007613 environmental effect Effects 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000012046 mixed solvent Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 229910017604 nitric acid Inorganic materials 0.000 description 2
- 210000004492 nuclear pore Anatomy 0.000 description 2
- 238000003199 nucleic acid amplification method Methods 0.000 description 2
- 238000005457 optimization Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- 238000001878 scanning electron micrograph Methods 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 238000005118 spray pyrolysis Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 230000008859 change Effects 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 239000003814 drug Substances 0.000 description 1
- 229940079593 drug Drugs 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000001493 electron microscopy Methods 0.000 description 1
- 238000011049 filling Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000009616 inductively coupled plasma Methods 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 238000011068 loading method Methods 0.000 description 1
- 238000005555 metalworking Methods 0.000 description 1
- 238000000100 multiple collector inductively coupled plasma mass spectrometry Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 238000001004 secondary ion mass spectrometry Methods 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Images
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J13/00—Colloid chemistry, e.g. the production of colloidal materials or their solutions, not otherwise provided for; Making microcapsules or microballoons
- B01J13/0095—Preparation of aerosols
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J6/00—Heat treatments such as Calcining; Fusing ; Pyrolysis
- B01J6/008—Pyrolysis reactions
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2004/00—Particle morphology
- C01P2004/01—Particle morphology depicted by an image
- C01P2004/03—Particle morphology depicted by an image obtained by SEM
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2004/00—Particle morphology
- C01P2004/60—Particles characterised by their size
-
- 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Dispersion Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
The invention relates to a micron-sized monodisperse uranium-thorium mixed particle, and a preparation method and a preparation system thereof. The method comprises the following steps: mixing a uranium-containing compound and a thorium-containing compound with a solvent to obtain a uranium-thorium mixed solution; under the condition of aerosol generation, enabling the uranium-thorium mixed solution to form uranium-thorium mixed liquid drops in an aerosol generation device, and enabling the uranium-thorium mixed liquid drops to settle downwards along a first vertical gas path of the sol generator under the action of carrier gas to enter a thermal decomposition device; and enabling the uranium-thorium mixed liquid drops to settle downwards along a second vertical gas path of the thermal decomposition device under the action of carrier gas, and carrying out thermal decomposition in the settling process to obtain uranium-thorium mixed particles. The uranium-thorium mixed particle prepared by the method can reach a micron level and has remarkable monodispersity, and the uranium-thorium mixed particle also has a regular spherical particle shape, narrower particle size distribution and more uniform uranium-thorium element composition; and this disclosure can also promote the preparation recovery efficiency of mixing the particle by a wide margin.
Description
Technical Field
The disclosure relates to the field of micron-sized particle preparation, in particular to micron-sized monodisperse uranium-thorium mixed particles and a preparation method and a preparation system thereof.
Background
Monodisperse, also called monodispersed systems or monodispersed systems, generally refer to dispersions in which the disperse phase has a single component and a narrow particle size distribution.
When nuclear material diffusion or nuclear events occur, it is desirable to track the source and history of the nuclear material, where the production time (age) of the material is an important analytical test. The age determination technology of nuclear materials is an important technical means for nuclear security and nuclear evidence collection. The nuclear guarantee environment sampling analysis technology is an effective means for detecting nuclear materials or nuclear activities. In the uranium conversion, uranium enrichment and element manufacturing processes, micron (mum) and submicron uranium-containing particles are released inside and outside a facility, an environment wiping sample is collected inside or around the nuclear facility, the uranium-containing particles are subjected to age detection, the ratio of Th-230 to U-234 in the uranium-containing particles is measured, the relevant information of the production time can be obtained, and whether illegal uranium enrichment activities exist is judged. In order to accurately measure the thorium-uranium ratio of uranium particles in an environmental sample, standard particles which are consistent with the properties of chemical components, physical forms, geometric dimensions and the like of an actual sample as much as possible are adopted to correct a measurement result. In addition, through the introduction of the standard particles, the traceability of the measurement can be established, and conditions are provided for effective international comparison of the measurement results.
Although a large number of researchers have studied the method for preparing microparticles in China, the preparation of monodisperse mixed microparticles is rarely involved at present, and no relevant literature is reported. Only the chinese institute of atomic energy science (CIAE) has successfully prepared micron-sized monodisperse uranium oxide particles in a close field.
In the world, in 2000, n.erdmann et al, the joint research institute of the european union (JRC) transuranics Institute (ITU), successfully produced monodisperse uranium oxide particles (monodisperse uranium oxide particles) having a particle size of 1 μm for the first time by aerosol spray pyrolysis, which is mature in uranium oxide particle production, and the research groups have turned to the study of the production of plutonium particles and mixed particles, as described in detail below. In 2003, zitouni Ould-Dada et al also produced quasi-monodisperse uranium oxide particles by sol spray pyrolysis, which had particle size distributions in the range of 0.13 to 1.37 μm and failed to satisfy the requirement of monodispersion. By 2005, y.j.park et al produced microparticles using an aerosol generating device: after obtaining the aerosol, siO with the grain diameter of 5, 10, 15 and 20 mu m is formed by gravity sedimentation and ignition2The particles, wherein U-235 with the abundance of 5% is adsorbed, are used as standard substances for fission track analysis, and although the particles prepared by the method have better dispersity, the particle size is larger than that of an environmental sample. In 2010, the ITU previously developed the basis for monodisperse uranium oxide particlesIn the above, there have been continued developments of particles of monodisperse plutonium and particles of mixed uranium plutonium for measuring uranium and plutonium ion yields in SIMS.
The related art disclosed so far includes a technique for producing monodisperse uranium plutonium mixed particles established by ITU and a technique for producing monodisperse uranium oxide particles developed by CIAE. The technology for preparing the monodisperse uranium plutonium mixed particles established by ITU adopts a device framework of a preheating device, a neutralizer, a double gas path (variable flow rate) and a three-muffle furnace; preheating is added on a dilution gas path; reducing particle agglomeration by adopting an electrostatic neutralizer; the flow rate of carrier gas is from high to low (the flow rate of carrier gas is 55L/min during preheating and 8L/min during thermal decomposition); besides the preparation gas path, an auxiliary gas path is added for cleaning; three muffle furnaces are connected in series for gradual temperature rise to promote thermal decomposition of particles. The whole equipment architecture of the scheme is complex (13 pieces of various equipment are needed to work cooperatively), the preparation process is complicated (the steps of aerosol preparation, desolvation, static electricity removal, gradual heating thermal decomposition, cooling, collection, tail gas treatment and the like are covered), the preparation parameter control and optimization difficulty is high, the prepared sample loss is large, and the recovery rate is low. The technology for preparing the monodisperse uranium oxide particles developed by CIAE adopts a device framework of 'preheating, neutralizer, single gas path (constant flow rate) and single muffle furnace'; reducing particle agglomeration by adopting an electrostatic neutralizer; preheating is added at the rear end of the device; the carrier gas flow is constant (35-45L/min); carrying out thermal decomposition by adopting a single muffle furnace; the technology optimizes the gas path of the carrier gas and the heating process, and 9 devices work cooperatively. Although the preparation technology of the monodisperse uranium oxide particles developed by CIAE simplifies the equipment architecture, the recovery rate of the prepared particles is still low, and is only about 1.2%.
Disclosure of Invention
The purpose of the disclosure is to provide micron-sized monodisperse uranium-thorium mixed particles, a preparation method and a preparation system thereof, which are used for preparing micron-sized monodisperse uranium-thorium mixed particles with regular appearance, narrow particle size distribution and consistent ratio of uranium to thorium, and obviously improve the preparation recovery rate of the particles.
In order to achieve the above object, a first aspect of the present disclosure provides a method for preparing micron-sized monodisperse uranium-thorium mixed particles, including the following steps: mixing a uranium-containing compound and a thorium-containing compound with a solvent to obtain a uranium-thorium mixed solution; under the condition of aerosol generation, enabling the uranium-thorium mixed solution to form uranium-thorium mixed liquid drops in an aerosol generation device, and enabling the mixed liquid drops to settle downwards along a first vertical gas path of the sol generator under the action of carrier gas to enter a thermal decomposition device; and enabling the uranium-thorium mixed liquid drops to settle downwards along a second vertical gas path of the thermal decomposition device under the action of carrier gas, and performing thermal decomposition in the settling process to obtain the uranium-thorium mixed particles.
Optionally, the uranium-containing compound is one or two of uranyl nitrate and uranyl sulfate, and is preferably uranyl nitrate; the thorium-containing compound is one or two of thorium nitrate and thorium sulfate, preferably thorium nitrate; the solvent is one or more of isopropanol, ethanol, acetone and water, and preferably is isopropanol.
Optionally, in the uranium-thorium mixed solution, the uranium content is 1 × 10-6~1×10-4g/ml, preferably 5X 10-6~×10-5g/ml; thorium content of 1X 10-6~1×10-4g/ml, preferably 5X 10-6~5×10-5g/ml。
Optionally, the aerosol generating conditions comprise: in the vibrating hole aerosol generating device, the flow rate of carrier gas is 40-50L/min, and the carrier gas is compressed air; the vibration frequency is 40-60 kHz; the sample introduction rate is 1.0-4.0 multiplied by 10-3cm/s; the stable pressure is 275-345 KPa.
Optionally, the conditions of the thermal decomposition include: the thermal decomposition temperature is 800-900 ℃, and the thermal decomposition is carried out in a muffle furnace.
Optionally, the method further comprises: cooling the mixed particles obtained by thermal decomposition in a third vertical gas path of a cooler at the temperature of 5-25 ℃, wherein optionally, the cooler adopts cooling water as a cooling medium; and collecting and filtering the cooled mixed particles to obtain the micron-sized monodisperse uranium-thorium mixed particles.
In a second aspect of the present disclosure, micron-sized monodisperse uranium-thorium mixed particles are provided, which are prepared according to the method of the first aspect of the present disclosure.
Optionally, the content ratio of the uranium-containing oxide and the thorium-containing oxide in the uranium-thorium mixed particles is (100; the particle size of the uranium-thorium mixed particle is 0.1-3 mu m.
The third aspect of the disclosure provides a system for preparing micron-sized monodisperse uranium-thorium mixed particles, which comprises an aerosol generating device and a thermal decomposition device; the aerosol generating device is provided with a uranium-thorium mixed solution inlet, a carrier gas inlet and a mixed liquid drop outlet; along the height direction of the aerosol generating device, the uranium-thorium mixed solution inlet is arranged at the top of the aerosol generating device, and the mixed liquid drop outlet is arranged at the bottom of the aerosol generating device, so that a first vertical gas path is formed between the uranium-thorium mixed solution inlet and the mixed liquid drop outlet and is used for mixed liquid drop sedimentation; the carrier gas inlet is arranged on the side wall of the aerosol generating device and used for providing carrier gas for the system; the thermal decomposition device is provided with a mixed liquid drop inlet and a mixed particle outlet, and the mixed liquid drop inlet is communicated with the mixed liquid drop outlet of the aerosol generating device through a first vertical pipeline; the thermal decomposition device is arranged below the aerosol generating device along the material flowing direction; the mixed liquid drop inlet and the mixed particle outlet are respectively arranged at the top and the bottom of the thermal decomposition device so as to form a second vertical gas path in the thermal decomposition device for enabling the mixed liquid drops from the aerosol generating device to continue to settle and to be thermally decomposed in the settling process.
Optionally, the system further comprises an air compressor, wherein a compressed air outlet of the air compressor is communicated with a carrier gas inlet of the aerosol generating device; the mixed particle outlet of the thermal decomposition device is communicated with the post-treatment device; optionally, in the vertical direction, the post-treatment device comprises a cooling device, a collecting membrane and a filter which are sequentially communicated from top to bottom; the top of the cooling device is provided with a mixed particle cooling inlet which is communicated with a mixed particle outlet of the thermal decomposition device through a second vertical pipeline; a mixed particle cooling outlet is formed at the bottom of the cooling device, and a third vertical gas path is formed between the mixed particle cooling inlet and the mixed particle cooling outlet and is used for cooling the mixed particles from the thermal decomposition device in the sedimentation process of the third vertical gas path; optionally, the system further comprises a cooling water circulation device for circulating cooling to the cooling device; optionally, the first vertical pipe and the second vertical pipe are quartz pipes; optionally, the aerosol generating device is a vibrating-orifice aerosol generating device and the thermal decomposition device is a split muffle.
Through the technical scheme, the disclosure provides micron-sized monodisperse uranium-thorium mixed particles and a preparation method and a preparation system thereof. The uranium-thorium mixed particle prepared by the method can reach a micron level and has remarkable monodispersity, and the uranium-thorium mixed particle also has a regular spherical particle shape, narrower particle size distribution and more uniform uranium-thorium element composition; and the preparation recovery efficiency of the mixed particles can be greatly improved. On the preparation system. The method improves the framework of the instrument and equipment, changes the original horizontal preparation pipeline into a vertical preparation pipeline, effectively reduces the loss of particles and improves the yield of the particles; in addition, the vertical pipeline can reduce the stress of liquid drops and particles in different directions in the preparation process, and is beneficial to preparing mixed particles. The preparation process is greatly simplified, the core link of the preparation of the monodisperse uranium-thorium mixed particles is defined, the non-core link is simplified, the preparation processes of aerosol preparation, thermal decomposition, cooling and collection are finally formed, and the influence of the non-essential link is reduced; through simplifying the flow, the auxiliary equipment framework is adjusted, the equipment is simplified, the pipeline is shortened, the particle loss is reduced, and the particle recovery rate is improved.
Additional features and advantages of the disclosure will be set forth in the detailed description which follows.
Drawings
The accompanying drawings, which are included to provide a further understanding of the disclosure and are incorporated in and constitute a part of this specification, illustrate embodiments of the disclosure and together with the description serve to explain the disclosure without limiting the disclosure. In the drawings:
fig. 1 is a schematic diagram of an apparatus of a system for preparing micron-sized monodisperse uranium-thorium mixed particles provided by the present disclosure;
FIG. 2 is a scanning electron microscope image of uranium-thorium mixed particles prepared in example 1;
FIG. 3 is a particle size distribution diagram of uranium-thorium mixed particles prepared in example 1;
fig. 4 is a scanning electron microscope image of uranium-thorium bulk microparticles prepared in example 2;
FIG. 5 is a particle size distribution diagram of uranium-thorium mixed particles prepared in example 2;
FIG. 6 is a scanning electron micrograph of uranium-thorium mixed particles prepared in example 3;
FIG. 7 is a particle size distribution diagram of uranium-thorium mixed particles prepared in example 3;
FIG. 8 is a scanning electron micrograph of uranium-thorium mixed particles prepared in example 4;
fig. 9 is a particle size distribution diagram of the uranium-thorium bulk blended microparticles prepared in example 4;
fig. 10 is a scanning electron microscope image of the uranium-thorium mixed microparticle prepared in comparative example 1.
Description of the reference numerals
1-aerosol generating device, 2-thermal decomposition device, 3-cooling device, 4-collecting membrane, 5-filter, 6-air compressor, 7-cooling water circulating device, 8-vacuum pump, 9-first vertical pipeline, 10-second vertical pipeline
Detailed Description
The following detailed description of the embodiments of the disclosure refers to the accompanying drawings. It should be understood that the detailed description and specific examples, while indicating the present disclosure, are given by way of illustration and explanation only, not limitation.
In the present disclosure, unless otherwise specified, the terms "first", "second", and the like are used only for distinguishing different components and do not have actual meanings such as the order of connection between the front and rear. In the present disclosure, the use of directional words such as "upper" and "lower" are upper and lower in the normal use state of the device, and "inner" and "outer" are in terms of the device profile.
The first aspect of the disclosure provides a method for preparing micron-sized monodisperse uranium-thorium mixed particles, which comprises the following steps:
mixing a uranium-containing compound and a thorium-containing compound with a solvent to obtain a uranium-thorium mixed solution;
under the condition of aerosol generation, enabling the uranium-thorium mixed solution to form uranium-thorium mixed liquid drops in an aerosol generation device, and enabling the mixed liquid drops to settle downwards along a first vertical gas path of the sol generator under the action of carrier gas to enter a thermal decomposition device;
and enabling the uranium-thorium mixed liquid drops to settle downwards along a second vertical gas path of the thermal decomposition device under the action of carrier gas, and performing thermal decomposition in the settling process to obtain the uranium-thorium mixed particles.
The uranium-thorium mixed particle prepared by the method can reach a micron level and has remarkable monodispersity, and the uranium-thorium mixed particle also has a regular spherical particle shape, narrower particle size distribution and more uniform uranium-thorium element composition; and the preparation recovery efficiency of the mixed particles can be greatly improved. The method changes the original horizontal preparation pipeline into the vertical preparation pipeline, effectively reduces the particle loss and improves the particle yield; in addition, the vertical pipeline can reduce the stress of liquid drops and particles in different directions in the preparation process, and is beneficial to preparing mixed particles. The method greatly simplifies the preparation process, defines the core link of the preparation of the monodisperse uranium-thorium mixed particles, simplifies the non-core link, finally forms the preparation processes of aerosol preparation, thermal decomposition, cooling and collection, reduces the influence of the non-essential link, and simplifies the process, the auxiliary equipment framework adjustment, simplifies the equipment, shortens the pipeline, reduces the particle loss and improves the particle recovery rate.
In one embodiment, the uranium-containing compound is one or two of uranyl nitrate and uranyl sulfate, preferably uranyl nitrate; the thorium-containing compound is one or two of thorium nitrate and thorium sulfate, preferably thorium nitrate; the solvent is one or more of isopropanol, ethanol, acetone and water, and is preferably isopropanol.
According to the method, a commonly used hydroalcoholic mixed solvent is changed into a single isopropanol as a solvent, so that the surface tension of prepared droplets is increased, uranium-thorium segregation is effectively inhibited, and the preparation of mixed particles is facilitated. In addition, the volatility of the isopropanol solvent is superior to that of the original water-alcohol mixed solvent, and the simplification and optimization of an instrument framework are facilitated. And the volatility of the solvent is improved, so that feasibility is provided for optimizing the processes of heating, preheating, desolvation and the like in a preparation process, and a prerequisite is provided for realizing the preparation of the monodisperse uranium-thorium mixed particles.
In one embodiment, the uranium-thorium mixed solution has a uranium content of 1 × 10-6~1×10-4g/ml, preferably 5X 10-6~5×10-5g/ml; thorium content of 1X 10-6~1×10-4g/ml, preferably 5X 10-6~5×10-5g/ml。
In one embodiment, the aerosol generating conditions comprise: in the vibrating hole aerosol generating device, the flow rate of carrier gas is 40-50L/min, and the carrier gas is compressed air; the vibration frequency is 40-60 kHz; the sample introduction rate is 1.0-4.0 multiplied by 10-3cm/s; the stable pressure is 275-345 KPa.
In one embodiment, the conditions of the thermal decomposition include: the thermal decomposition temperature is 800-900 ℃, and the thermal decomposition is carried out in a muffle furnace.
Preparation parameters are optimized in the preparation process, parameters closely related to the preparation of the uranium-thorium mixed particles are refined and defined, and the parameters comprise carrier gas flow, heating temperature, vibration frequency, sampling speed, stable pressure and the like, wherein the effect of preparing the uranium-thorium mixed particles is directly influenced by the change of any parameter, and the recovery rate of micron-sized monodisperse uranium-thorium mixed particles and the performance of the uranium-thorium mixed particles can be further improved.
In one embodiment, the method further comprises: cooling the mixed particles obtained by thermal decomposition in a third vertical gas path of a cooler at the temperature of 5-25 ℃, wherein optionally, the cooler adopts cooling water as a cooling medium;
and collecting and filtering the cooled mixed particles to obtain the micron-sized monodisperse uranium-thorium mixed particles.
The sedimentation cooling is carried out in the third vertical gas path of the cooling device, so that the loss rate of mixed particles is further reduced.
In a second aspect of the present disclosure, micron-sized monodisperse uranium-thorium mixed particles are provided, which are prepared according to the method of the first aspect of the present disclosure.
In one embodiment, the weight content ratio of the uranium-containing oxide to the thorium-containing oxide in the uranium-thorium mixed particulate is constant, and the ratio is (100; the particle sizes of the uranium-thorium mixed particles are basically consistent, and the particle size range is 0.1-3 mu m. The uranium-thorium mixed particles prepared by the method are regular spherical particles; the ratio of uranium to thorium in the prepared uranium-thorium mixed solution is consistent with that in the prepared uranium-thorium mixed particle, so that the segregation phenomenon is avoided; and the particle size distribution is narrow, and the obvious monodispersity is presented.
The micron-sized monodisperse uranium-thorium mixed particle provided by the disclosure can be applied to the fields of nuclear guarantee and nuclear law evidence.
In a third aspect of the present disclosure, a system for preparing micron-sized monodisperse uranium-thorium mixed particles is provided, as shown in fig. 1, the system includes an aerosol generating device 1 and a thermal decomposition device 2;
the aerosol generating device 1 is provided with a uranium-thorium mixed solution inlet, a carrier gas inlet and a mixed liquid drop outlet; along the height direction of the aerosol generating device 1, a uranium-thorium mixed solution inlet is arranged at the top of the aerosol generating device 1, and a mixed liquid drop outlet is arranged at the bottom of the aerosol generating device 1, so that a first vertical gas path is formed between the uranium-thorium mixed solution inlet and the mixed liquid drop outlet and is used for mixed liquid drop sedimentation; the carrier gas inlet is arranged on the side wall of the aerosol generating device and is used for providing carrier gas for the system;
the thermal decomposition device 2 is provided with a mixed liquid drop inlet and a mixed particle outlet, and the mixed liquid drop inlet is communicated with the mixed liquid drop outlet of the aerosol generating device 1 through a first vertical pipeline 9; the thermal decomposition device 2 is arranged below the aerosol generating device 1 along the material flowing direction; the mixed liquid drop inlet and the mixed particle outlet are respectively arranged at the top and the bottom of the thermal decomposition device 2 so as to form a second vertical gas path in the thermal decomposition device 2 for enabling the mixed liquid drops from the aerosol generating device 1 to continue to settle and to be thermally decomposed in the process of settling.
In one embodiment, the aerosol generating device 1 is a vibrating-hole aerosol generating device and the thermal decomposition device 2 is a split muffle.
In one embodiment, the first vertical pipe and the second vertical pipe are quartz pipes.
In one embodiment, as shown in fig. 1, the system further comprises an air compressor 6, wherein a compressed air outlet of the air compressor 6 is communicated with a carrier gas inlet of the aerosol generating device 1;
the mixed fine particle outlet of the thermal decomposition device 2 is communicated with a post-treatment device.
In one embodiment, as shown in fig. 1, the post-treatment device comprises a cooling device 3, a collecting membrane 4 and a filter 5 which are arranged in communication from top to bottom in the vertical direction; the top of the cooling device 3 is provided with a mixed particle cooling inlet which is communicated with a mixed particle outlet of the thermal decomposition device 2 through a second vertical pipeline 10; the bottom of the cooling device 3 is provided with a mixed particle cooling outlet, and a third vertical gas path is formed between the mixed particle cooling inlet and the mixed particle cooling outlet and used for cooling the mixed particles from the thermal decomposition device 2 in the sedimentation process of the third vertical gas path.
In one embodiment, as shown in fig. 1, the system further comprises a cooling water circulation device 7 for circulating cooling water to the cooling device 3. Specifically, the cooling device 3 comprises a cooling pipe and a cooling water circulation layer, the cooling water circulation layer is coated on the outer side wall of the cooling pipe, and the third vertical gas path is arranged in the cooling pipe; the cooling water circulation layer is provided with a cooling water inlet and a warm water outlet, the cooling water circulation device 7 is provided with a cooling water outlet and a warm water inlet, the cooling water outlet of the cooling water circulation device 7 is communicated with the cooling water inlet of the cooling device 3, and the warm water outlet of the cooling device 3 is communicated with the warm water inlet of the cooling water circulation device 7.
In one embodiment, the present disclosure provides a system in which the passage from the aerosol generating device 1 to the thermal decomposition device 2 to the cooling device 3 to the collecting membrane 4 to the filter 5 is vertical in the vertical direction, thereby reducing the loss of particles and improving the recovery rate of particles.
In one embodiment, the system provided by the present disclosure does not use an electrostatic neutralizer, simplifies equipment, shortens piping, reduces particle loss, and improves particle recovery.
In one embodiment, the system further comprises a vacuum pump 8, and an input port of the vacuum pump 8 is communicated with the filter 5 for pumping air to provide a negative pressure environment.
The specific process for preparing the micron-sized monodisperse uranium-thorium mixed particles by adopting the system shown in the figure 1 of the disclosure comprises the following steps: introducing a uranium-thorium mixed solution into the upper part of a first vertical gas path of the aerosol generating device 1 through a uranium-thorium mixed solution inlet, introducing a carrier gas into the first vertical gas path of the aerosol generating device 1 through a carrier gas inlet, settling the uranium-thorium mixed solution in the first vertical gas path under the action of the carrier gas and the self gravity, and forming uranium-thorium mixed liquid drops in the settling process; the mixed liquid drops enter the first vertical pipeline 9 to continue to settle; enabling the uranium-thorium mixed liquid drops to enter the position above a second vertical gas path of the thermal decomposition device through the mixed liquid drop inlet, continuously settling under the action of carrier gas, and thermally decomposing at high temperature to form uranium-thorium mixed particles; the uranium-thorium mixed particles enter a second vertical pipeline 10 through a mixed particle outlet, then enter a third vertical gas path of the cooling device 3 through a mixed particle cooling inlet, continue to settle under the action of the mixed particle cooling inlet, and simultaneously exchange heat with circulating cooling water for cooling; the cooled mixed fine particles are deposited on the collecting membrane 4 through the mixed fine particle cooling outlet, collected, and then filtered through the filter 5.
The present disclosure is further illustrated by the following examples.
The preparation apparatus and reaction reagents used in the following examples include:
medical pure oil-free air compressor (WSC 22140B Shanghai Huaishi electromechanical Co., ltd.), precision pressure reducing valve (IR 2020-02 Japan SMC Co., ltd.), vibrating hole aerosol generator (VOAG-3450 American TSI Co., ltd.), quartz pipe (Beijing Kort quartz glass works), split tube muffle furnace and its temperature control box (Beijing century metalworking electric furnace Co., ltd.), cooling water circulation device (CFT 300 American Thermo Electron Corporation), vacuum pump (V600 German WIGGENS Labortechnik GmbH), ten thousandth electronic balance (Germany Saedodes GmbH), collecting film (China atomic energy science institute of Physics), filter (Germany FestoAG & Co.
Isopropanol, analytical pure AR, chemical reagents ltd of the national drug group;
uranyl nitrate, analytically pure, chinese pharmaceutical company;
thorium nitrate, analytically pure, kralmar.
In the following examples and comparative examples, tests were carried out including:
the appearance and appearance of the particles are analyzed by a Scanning Electron Microscope (SEM): the instrument is JSM-6360LV, JEOL company of Japan; the detection conditions include: amplification factor 5000, vacuum 30Pa, voltage 25kV.
The average particle size detection method comprises the following steps: single measurement statistics.
Particle size distribution of the particles: single measurement statistics.
The particle preparation recovery rate detection method comprises the following steps: and (5) theoretically calculating statistics.
The thorium-uranium ratio of the original solution and the dissolved particles in the solution is tested by ICP-MS: the instrument is an Isoprobe type multi-receiving inductively coupled plasma mass spectrometer MC-ICP-MS (GV company, UK), and the detection conditions comprise: working voltage 6000V, RF power 1100W, atomizer flow 0.85L/m.
The uniformity of uranium-thorium composition of the mixed particles is tested by SEM-EDX and SIMS: the instrument comprises the following steps: double focusing secondary ion mass spectrometry IMS-6f (CAMECA, france); the detection conditions include: the primary beam energy is 12.5KV, the sample high voltage is 5000V, and the field diaphragm is 1800 μm. The instrument comprises the following steps: high and low vacuum scanning electron microscope JSM-6360LV (JEOL corporation, japan), spectrometer AZtec (Oxford Instruments, UK); the detection conditions include: amplification factor 5000, vacuum 30Pa, voltage 25kV.
Example 1
This example was used to prepare monodisperse uranium-thorium hybrid microparticles.
Respectively weighing 0.89g of uranyl nitrate powder and 0.91g of thorium nitrate powder according to a nearly equal ratio (equal weight ratio);
dissolving the two powders in isopropanolPassing through a volumetric flask for constant volume, diluting step by step until the concentration is 4 multiplied by 10-5And (3) using a mixed solution of uranium and thorium in g/ml as an aerosol generating solution. Uranium-thorium bulk pellets were prepared using the system shown in fig. 1, according to the parameters in table 1 below.
TABLE 1
Condition parameter | Parameter selection |
Frequency of vibration of vibrating orifice | 52.5kHz |
The sample introduction rate is | 1.5×10-3cm/s |
Stabilized pressure | 310KPa |
Carrier gas flow rate | 50L/min |
Heating temperature of muffle furnace | 900℃ |
The preparation method comprises the following specific steps: (1) And (3) loading the uranium-thorium mixed solution into a sample injection injector of an aerosol generator, and forming monodisperse aerosol through the generator.
(2) And (3) carrying out high-temperature thermal decomposition on the monodisperse aerosol through 1 muffle furnace to form uranium-thorium mixed particles.
(3) The temperature of cooling water is set to be 15 ℃, and the high-temperature uranium-thorium mixed particles after thermal decomposition are collected on a nuclear pore membrane after being cooled, and the collection time is about 30 minutes.
The morphology image of the particle prepared in this example observed by SEM is shown in fig. 2. From the particle topography, the prepared particles are spherical, and have smooth surfaces and clear boundaries. The particle size distribution of the prepared particles is shown in figure 3. From the particle size distribution, it can be found that the prepared particles are relatively concentrated in particle size, wherein the number of the uranium-thorium mixed particles with the particle size of 2-3 mu m is 70% of the total number of all the uranium-thorium mixed particles, and the particles have monodispersity. The ratio (atomic number ratio) of thorium to uranium in the original solution and the solution after the particles were dissolved (the solvent for dissolving the particles was nitric acid) was 0.87 by ICP-MS, and it was confirmed by SEM-EDX and SIMS analysis that the composition of uranium and thorium in the mixed particles was uniform, i.e., the ratio of thorium to uranium in the single mixed particle was 0.87. The microparticle preparation recovery of this example was 5.1%.
Example 2
The same preparation method as that of example 1 was adopted, differing from example 1 only in that: weighing appropriate amount of uranyl nitrate and thorium nitrate powder according to a near-equal ratio, dissolving the powder into isopropanol, fixing the volume by a volumetric flask, and gradually diluting to a concentration of 5 × 10-6And (3) using a mixed solution of uranium and thorium in g/ml as an aerosol generating solution.
The morphology image of the prepared particles observed by SEM is shown in FIG. 4. From the particle topography, the prepared particles are spherical, and have smooth surfaces and clear boundaries. The particle size distribution of the prepared particles is shown in figure 5. From the particle size distribution, it can be found that the prepared particles have relatively concentrated particle sizes, wherein the number of the uranium-thorium mixed particles with the particle size of 1-1.2 mu m is 84% of the total number of all the uranium-thorium mixed particles, and the particles have monodispersity. The thorium-uranium ratio of the original solution and the solution after the particles are dissolved is 0.87 measured by ICP-MS, and SEM-EDX and SIMS analysis proves that the mixed particles have uniform uranium-thorium composition, namely the ratio of thorium to uranium in the single mixed particle is 0.87. The recovery rate of fine particles in this example was 4.7%.
Example 3
The same preparation method as that of example 2 was used, except that: uranium thorium blended microparticles were prepared according to the parameters in table 2 below.
TABLE 2
Condition parameter | Parameter selection |
Frequency of vibration of vibrating orifice | 47.7kHz |
The sample introduction rate is | 1.2×10-3cm/s |
Stabilized pressure | 320KPa |
Carrier gas flow rate | 40L/min |
Heating temperature of muffle furnace | 850℃ |
The morphology image of the prepared particles observed by SEM is shown in FIG. 6. From the particle topography, the prepared particles are spherical, and have smooth surfaces and clear boundaries. The particle size distribution of the prepared particles is shown in figure 7. From the particle size distribution, it was found that the particles were relatively concentrated in particle size, and among them, the uranium-thorium mixed particles having a particle size of 1.2 to 1.4 μm were 83% in number based on the total number of all the uranium-thorium mixed particles, and they were monodisperse. The ratio of thorium to uranium in the original solution and the solution after the particles are dissolved is 0.87 through ICP-MS (inductively coupled plasma-mass spectrometry), and the mixed particles are determined to be uniform in uranium and thorium composition through SEM-EDX and SIMS (simple Electron microscope-electron microscopy) analysis, so that the ratio of thorium to uranium in the single mixed particles is 0.87. The recovery rate of fine particles in this example was 5.2%.
Example 4
The same preparation method as in example 1 was used, except that: respectively weighing 9.74g of uranyl nitrate powder and 0.91g of thorium nitrate powder; dissolving the two powders in isopropanol, diluting to constant volume by volumetric flask, and gradually diluting until the uranyl nitrate concentration is 5 × 10-6g/ml, thorium nitrate concentration of 5X 10-7And (4) mixing uranium and thorium in g/ml to obtain the solution for generating aerosol.
The morphology image of the particles prepared in this example observed by SEM is shown in fig. 8. From the particle topography, the prepared particles are spherical, and have smooth surfaces and clear boundaries. The particle size distribution of the prepared particles is shown in figure 9. From the particle size distribution, it can be found that the prepared particles are relatively concentrated in particle size, wherein the number of the uranium-thorium mixed particles with the particle size of 1-1.2 mu m is 78% of the total number of all the uranium-thorium mixed particles, and the particles have monodispersity. The ratio (atomic ratio) of thorium to uranium in the original solution and the solution after the particles were dissolved (the solvent for dissolving the particles was nitric acid) was 0.09 by ICP-MS, and it was confirmed by SEM-EDX and SIMS analysis that the composition of uranium and thorium in the mixed particles was uniform, i.e., the ratio of thorium to uranium in the single mixed particle was 0.09. The microparticle preparation recovery of this example was 5.3%.
Comparative example 1
Weighing appropriate amount of uranyl nitrate powder and thorium nitrate respectively as powder according to nearly equal ratio (equal weight ratio), dissolving the two powders in isopropanol, fixing volume by volumetric flask, and diluting step by step to concentration of 5 × 10-6And (3) using a mixed solution of uranium and thorium in g/ml as an aerosol generating solution.
The uranium-thorium mixed particles were then prepared using the method disclosed in patent application CN 101891253B. The preparation method comprises the following specific steps: (1) Setting the vibration frequency of the vibrating hole aerosol generator to be 55.8kHz, setting the carrier gas flow to be 40L/min, filling the uranium-thorium mixed solution into a sample injection injector of the aerosol generator, and forming monodisperse aerosol through the generator.
(2) The monodisperse aerosol passes through a neutralizer to remove the charges on the surfaces of the aerosol droplets. And then preheating the carrier gas at the rear end of the neutralizer, setting the temperature of a heating belt to be 120 ℃, and heating the carrier gas to be about 79-80 ℃ to evaporate the solvent in the aerosol droplets to form solid particles.
(3) And carrying out high-temperature thermal decomposition on the obtained solid particles in 1 muffle furnace, wherein the heating temperature of the muffle furnace is 690-710 ℃, and finally forming the uranium-thorium mixed particles.
(4) And (3) setting the temperature of cooling water to be 15 ℃, collecting the uranium-thorium mixed particles subjected to thermal decomposition on a nuclear pore membrane after cooling, wherein the collecting time is about 30 minutes, and then filtering the collected uranium-thorium mixed particles to obtain the final uranium-thorium mixed particles.
The shape image of the prepared mixed particle observed by SEM is shown in FIG. 10. From the particle morphology graph, the prepared particles are nonspherical, irregular and loose in morphology; the uranium-thorium content in the mixed particles prepared in the comparative example is greatly different from that in the original solution, specifically, the uranium content in the original solution is 43.0 wt%, and the thorium content in the original solution is 57 wt%; the uranium content in the prepared particles was 67.9 wt%, and the thorium content was 32.1 wt%, indicating that there was significant segregation of the uranium-thorium element. The particulate recovery of this comparative example was 1.2%.
As can be seen from the comparison between the above examples 1 to 4 and the comparative example 1, the preparation recovery rate of the uranium-thorium mixed particles prepared by the method and the system provided by the application is higher, the particle shape of the uranium-thorium mixed particles is more regular, the particle size distribution is narrower, the monodispersity is better, the composition of uranium and thorium in the uranium-thorium mixed particles is uniform, and the uranium-thorium segregation phenomenon does not exist.
The preferred embodiments of the present disclosure are described in detail with reference to the accompanying drawings, however, the present disclosure is not limited to the specific details of the above embodiments, and various simple modifications may be made to the technical solution of the present disclosure within the technical idea of the present disclosure, and these simple modifications all belong to the protection scope of the present disclosure.
It should be noted that the various features described in the foregoing embodiments may be combined in any suitable manner without contradiction. In order to avoid unnecessary repetition, various possible combinations will not be separately described in this disclosure.
In addition, any combination of various embodiments of the present disclosure may be made, and the same should be considered as the disclosure of the present disclosure, as long as it does not depart from the spirit of the present disclosure.
Claims (17)
1. The method for preparing micron-sized monodisperse uranium-thorium mixed particles is characterized by comprising the following steps of:
mixing a uranium-containing compound and a thorium-containing compound with a solvent to obtain a uranium-thorium mixed solution;
under the condition of aerosol generation, enabling the uranium-thorium mixed solution to form uranium-thorium mixed liquid drops in an aerosol generation device, and enabling the uranium-thorium mixed liquid drops to settle downwards along a first vertical gas path of the aerosol generation device under the action of carrier gas to enter a thermal decomposition device;
and enabling the uranium-thorium mixed liquid drops to settle downwards along a second vertical gas path of the thermal decomposition device under the action of carrier gas, and performing thermal decomposition in the settling process to obtain the uranium-thorium mixed particles.
2. The method according to claim 1, wherein the uranium-containing compound is one or both of uranyl nitrate and uranyl sulfate; the thorium-containing compound is one or two of thorium nitrate and thorium sulfate; the solvent is one or more of isopropanol, ethanol, acetone and water.
3. A process according to claim 1 wherein the uranium containing compound is uranyl nitrate; the thorium-containing compound is thorium nitrate; the solvent is isopropanol.
4. The process of claim 1~3, wherein said uranium-thorium mixed solution has a uranium content of 1 x 10-6~1×10-4g/ml; thorium content of 1X 10-6~1×10-4g/ml。
5. The method according to claim 4, wherein the uranium-thorium mixed solution has a uranium content of 5 x 10-6~5×10-5g/ml; thorium content of 5X 10-6~5×10-5g/ml。
6. The method of claim 1, wherein the aerosol-generating conditions comprise: in a vibrating hole aerosol generating device, the flow rate of carrier gas is 40 to 50L/min, and the carrier gas is compressed air; the vibration frequency is 40 to 60kHz; the sample introduction rate is 1.0 to 4.0 × 10-3 cm/s; the stable pressure is 275 to 345KPa.
7. The method of claim 1, wherein the conditions of thermal decomposition comprise: the thermal decomposition temperature is 800 to 900 ℃, and the thermal decomposition is carried out in a muffle furnace.
8. The method of claim 1, further comprising:
cooling the mixed particles obtained by thermal decomposition in a third vertical gas path of a cooler at the temperature of 5-25 ℃;
and collecting and filtering the cooled mixed particles to obtain the micron-sized monodisperse uranium-thorium mixed particles.
9. The method of claim 8, wherein the cooler uses cooling water as a cooling medium.
10. Micron-sized monodisperse uranium-thorium hybrid particles, prepared according to the method of any of claims 1~9.
11. The uranium-thorium mixed microparticles according to claim 10, wherein a content ratio of the uranium-containing oxide to the thorium-containing oxide in the uranium-thorium mixed microparticles is in a range of (100) - (1:1); the particle size of the uranium-thorium mixed particle is 0.1-3 mu m.
12. A system for preparing micron-sized monodisperse uranium-thorium mixed particles is characterized by comprising an aerosol generating device (1) and a thermal decomposition device (2);
the aerosol generating device (1) is provided with a uranium-thorium mixed solution inlet, a carrier gas inlet and a mixed liquid drop outlet; along the height direction of the aerosol generating device (1), the uranium-thorium mixed solution inlet is arranged at the top of the aerosol generating device (1), and the mixed liquid drop outlet is arranged at the bottom of the aerosol generating device (1), so that a first vertical gas path is formed between the uranium-thorium mixed solution inlet and the mixed liquid drop outlet for mixed liquid drop sedimentation; the carrier gas inlet is arranged on the side wall of the aerosol generating device and used for providing carrier gas for the system;
the thermal decomposition device (2) is provided with a mixed liquid drop inlet and a mixed particle outlet, and the mixed liquid drop inlet is communicated with the mixed liquid drop outlet of the aerosol generating device (1) through a first vertical pipeline (9); the thermal decomposition device (2) is arranged below the aerosol generating device (1) along the material flowing direction; the mixed liquid drop inlet and the mixed particle outlet are respectively arranged at the top and the bottom of the thermal decomposition device (2) so as to form a second vertical gas path in the thermal decomposition device (2) for enabling the mixed liquid drops from the aerosol generating device (1) to continue to settle and to be thermally decomposed in the settling process.
13. The system of claim 12, further comprising an air compressor (6), wherein a compressed air outlet of the air compressor (6) is in communication with a carrier gas inlet of the aerosol generating device (1);
the mixed particle outlet of the thermal decomposition device (2) is communicated with a post-treatment device.
14. The system according to claim 13, characterized in that, in the vertical direction, the post-treatment device comprises a cooling device (3), a collecting membrane (4) and a filter (5) which are arranged in communication from top to bottom; the top of the cooling device (3) is provided with a mixed particle cooling inlet which is communicated with a mixed particle outlet of the thermal decomposition device (2) through a second vertical pipeline (10); and a mixed particle cooling outlet is formed at the bottom of the cooling device (3), and a third vertical gas path is formed between the mixed particle cooling inlet and the mixed particle cooling outlet and is used for cooling the mixed particles from the thermal decomposition device (2) in the sedimentation process of the third vertical gas path.
15. System according to claim 14, characterized in that it further comprises cooling water circulation means (7) for circulating cooling of the cooling means (3).
16. The system of claim 14, wherein the first vertical pipe and the second vertical pipe are quartz pipes.
17. The system of claim 13, wherein the aerosol generating device is a vibrating-orifice aerosol generating device and the thermal decomposition device is a split muffle.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202111028388.2A CN113753956B (en) | 2021-09-02 | 2021-09-02 | Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202111028388.2A CN113753956B (en) | 2021-09-02 | 2021-09-02 | Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof |
Publications (2)
Publication Number | Publication Date |
---|---|
CN113753956A CN113753956A (en) | 2021-12-07 |
CN113753956B true CN113753956B (en) | 2022-11-01 |
Family
ID=78792754
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202111028388.2A Active CN113753956B (en) | 2021-09-02 | 2021-09-02 | Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN113753956B (en) |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3151085A (en) * | 1960-05-12 | 1964-09-29 | Grace W R & Co | Method for the preparation of metal oxide sols |
CN101891253B (en) * | 2010-07-16 | 2012-08-22 | 中国原子能科学研究院 | Preparation method of monodisperse micron-sized uranium oxide particles |
CN103165206B (en) * | 2011-12-15 | 2015-10-28 | 中国核动力研究设计院 | Thorium uranium mixed oxide ceramic microsphere preparation method |
CN107833645B (en) * | 2017-10-26 | 2020-02-07 | 中国科学院上海应用物理研究所 | Preparation method of thorium-based mixed oxide ceramic microspheres |
-
2021
- 2021-09-02 CN CN202111028388.2A patent/CN113753956B/en active Active
Also Published As
Publication number | Publication date |
---|---|
CN113753956A (en) | 2021-12-07 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US20230415231A1 (en) | Reactive metal powders in-flight heat treatment processes | |
CN101284220B (en) | Quasi-monodispersed submicron aerosol generating device using vaporization condensation process | |
CN109742344B (en) | Aluminum oxide coated high-nickel cathode material with low free lithium, preparation method and application | |
CN103570020B (en) | A kind of submicron narrow particle size distribution type tungsten and tungsten carbide powder and preparation method thereof | |
CN102419277B (en) | Identification detection method of nano titanium dioxide in sun-screening cosmetic | |
Neumeier et al. | Microparticle production as reference materials for particle analysis methods in safeguards | |
CN108620600B (en) | High-purity platinum black with large specific surface area and preparation method thereof | |
CN103801706B (en) | Molybdenum powder and preparation method thereof for ceramic metallization | |
CN113753956B (en) | Micron-sized monodisperse uranium-thorium mixed particle and preparation method and preparation system thereof | |
CN111299602B (en) | Method for preparing ruthenium nanoparticles without container | |
CN106623952B (en) | A kind of titanium of the micro- hydrogenation in surface or the preparation method of titanium alloy powder | |
CN113800530A (en) | Submicron spherical silicon micro powder, preparation method and application thereof | |
CN108714699B (en) | It is a kind of using silver sulfide induction prepare Active silver powder method and its silver powder obtained | |
CN101891253B (en) | Preparation method of monodisperse micron-sized uranium oxide particles | |
CN113087755B (en) | Method for preparing betamethasone superfine particles | |
CN111446446B (en) | CoCO (cobalt oxide) 3 /RGO composite material, preparation method thereof and application thereof in lithium battery electrode material | |
CN104817107B (en) | A kind of method of preparing black titanium dioxide B phase and anatase-phase nano particle | |
Middendorp et al. | Micro particle suspensions for preparation of reference materials for particle analysis methods in safeguards | |
US11786882B2 (en) | Device and method for magnetic field-assisted simulation of zero-microgravity fame synthesis of nanoparticles | |
CN102059345A (en) | Method for preparing cobalt-nickel metal or alloy powder by solution nebulization method | |
CN109338339A (en) | A kind of accordion three-dimensional porous ZnO film and preparation method thereof | |
US20230110739A1 (en) | Manufacture of particulate reference materials | |
CN219596590U (en) | Controllable atomizing balling reactor of air-conditioning flow field | |
KR101739027B1 (en) | Uranium nanoparticle and method for manufacturing the same | |
CN109317116A (en) | A kind of compound resin and preparation method thereof and recovery method to palladium in nitric acid medium |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |