CN110223789A - Manufacturing method, inertia base dispersion fuel pellet and the integrated fuel stick and its manufacturing method of high uranium density coated fuel particles - Google Patents
Manufacturing method, inertia base dispersion fuel pellet and the integrated fuel stick and its manufacturing method of high uranium density coated fuel particles Download PDFInfo
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- CN110223789A CN110223789A CN201910377421.9A CN201910377421A CN110223789A CN 110223789 A CN110223789 A CN 110223789A CN 201910377421 A CN201910377421 A CN 201910377421A CN 110223789 A CN110223789 A CN 110223789A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
- G21C21/10—Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching by rolling, e.g. "picture frame" technique
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
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- 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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a kind of manufacturing method of high uranium density coated fuel particles, inertia base dispersion fuel pellet and integrated fuel stick and its manufacturing method, the manufacturing method of high uranium density coated fuel particles includes S1, the mixed-powder that U-Si compound is made using smelting process；S2, according to the difference of density between powder different in the mixed-powder, each powder of the mixed-powder is separated using centrifugal separation；S3, the U that will be isolated3Si2Powder is mixed with binder, and the smooth spherical core in surface is made；S4, it is sequentially depositing to form multilayer coating structure layer by vapour deposition process on the core surface, high uranium density coated fuel particles is made.The present invention obtains the higher UxSiy powder of purity with smelting process cooperation powder centrifugal separation, realizes continuous production；It replaces sol-gal process to prepare the core of coated fuel particles using powder metallurgic method, reduces the pollution that chemical waste fluid generates, simplify operation, reduce preparation cost, improve economy.
Description
Technical field
The present invention relates to nuclear fuel technical field more particularly to a kind of manufacturing method of high uranium density coated fuel particles,
Inertia base dispersion fuel pellet and its manufacturing method, integrated fuel stick and its manufacturing method.
Background technique
The development of high temperature gas cooled reactor and coated fuel particles succeed in developing and development has mature close relationship.Industry
There is a spherical UO in the coated fuel particles that metaplasia produces2Core, it is outer that 4 layers of closure ball are wrapped up by gas phase deposition technology
Shell, respectively loose buffer layer, dense barrier layer, structural support sealant, dense barrier layer (i.e. TRISO particle, if only two
Layer is then BISO particle).The main function of this several layer material is the release for constraining fissioner, stopping fission product.
Last century, U.S.'s Oak Ridge use for laboratory chemical method produce carbide microballoon, and subsequent oxycarbide microballoon also succeeds
It generates, has broken the tradition for using oxide for a long time as core, the product of carbide and oxygen is wrapped by layer and is blocked in
Intragranular, high uranium density core improve whole uranium loading amount and thermal conductivity, and many experimental results show that carbide core particle has
Biggish application space, the reference fuel core that U.S. Department of Energy develops carbide, oxycarbide microballoon as high temperature gas cooled reactor
Core material.
IMDP pellet (Inert Matrix Dispersion Pellet, IMDP), be by TRISO coated fuel particles more
It dissipates and is solidificated in cylindrical SiC matrix or metallic matrix.SiC matrix or metallic matrix not only act as structural support effect, simultaneously
Also have radiation resistance, corrosion-resistant, shielding fission product release effect.The U.S., Japan are successive with multiple research institutions of South Korea
Carry out the research of TRISO coated fuel particles and inertia base preparation of fuel.China is in Tsinghua University and center north nuclear fuel
Element Co., Ltd sets up technical grade coated fuel particles and graphite spheric fuel element production line.To solve in manufacture to combustion
Expect the limitation of volume share, the high uranium density U-Si compound U in the U.S.3Si2Ceramics, disperse form fuel slab in basis material, can
The moderate finite deformation for avoiding irradiation unstability from generating, successful application and dispersion fuel in certain feature.
Currently, the method that the research institutions such as the U.S., South Korea use for the preparation of cladding fuel core and IMDP/FCM preparation
Mainly: smelting process, atomization preparation cladding fuel core powder；Chemical method, that is, sol-gel method prepares carbide, nitridation
Object, oxycarbide coat fuel core；Vapour deposition process prepares four layers of TRISO clad, and covering material includes ZrC, SiC etc.；
Hot pressed sintering prepares inertia base dispersion fuel pellet, by cladding fuel core disperse in ceramics or metallic matrix, integration system
For at fuel rod.However, both at home and abroad temporarily without UxSiy coated fuel particles preparation method.Explore UxSiy coated fuel particles and
The preparation process of the IMDP pellet of UxSiy core is one of the important research direction of cladded type fuel.
Traditional coated fuel particles use UO2As core, however UO2Thermal conductivity is low, under high temperature and radiation environment, heat
Conductance can be also remarkably decreased.According to present Research, TRISO grain volume fraction content not more than 40% in IMDP fuel,
There was only about eighth volume and due to the design feature of TRSIO itself, in entire particle is uranium dioxide fuel, therefore
The uranium loading amount of fuel pellet entirety is very low, and economy is very poor, it is difficult to meet the requirement of commercial presurized water reactor at present.It improves
TRISO uranium loading amount expands the research hotspot that application has become various countries.
The preparation process of UxSiy coated fuel particles consists of three parts: the preparation of UxSiy powder, the preparation of TRISO core,
Clad preparation.UxSiy powder is prepared frequently with smelting process and atomization.Smelting process production cost is low, and ingot casting uniformity is good, easily
Realize large-scale production, but ingot casting is also easy to produce a large amount of impurity, is not easy to separate powder and purified.The powder of atomization preparation
Good fluidity, and fuel element thermal conductivity made of powder is high, but atomization is not easy to accomplish scale production.
TRISO core prepares common chemical method, that is, sol-gal process, and chemical method is suitable for oxide, carbide and nitride
The preparation of equal coated particles core, technical maturity, the core good sphericity of coated particle.Preparation for UxSiy core, is not easy
It finds and suitably dissolves precursor solution, therefore be not available chemical method preparation UxSiy fuel core.In addition, chemical method is not easy to advise
Modelling production, it is at high cost and have a small amount of waste liquor contamination.
Summary of the invention
The technical problem to be solved in the present invention is that providing a kind of high uranium density, the cladding combustion of the high uranium density of high heat conductance
The manufacturing method for expecting particle, inertia base dispersion fuel pellet and its manufacturing method made of the high uranium density coated fuel particles,
Integrated fuel stick and its manufacturing method made of the high uranium density coated fuel particles.
The technical solution adopted by the present invention to solve the technical problems is: providing a kind of high uranium density coated fuel particles
Manufacturing method, comprising the following steps:
S1, the mixed-powder that U-Si compound is made using smelting process；
S2, according to the difference of density between powder different in the mixed-powder, using centrifugal separation by the mixing
Each powder of powder is separated；
S3, the U that will be isolated3Si2Powder is mixed with binder, and the smooth spherical core in surface is made；
S4, it is sequentially depositing to form multilayer coating structure layer by vapour deposition process on the core surface, high uranium density packet is made
Cover fuel particle.
Preferably, in step S1, the size controlling of the mixed-powder is at 40 μm -80 μm.
Preferably, step S1 includes:
S1.1, U-Si compound is placed in vacuum melting furnace, vacuum degree is down to 20MPa hereinafter, power transmission, melts according in furnace
Change situation heating temperature, until U-Si compound is completely melt；
S1.2, continuous mechanical stirring, until stopping stirring when temperature is 1500 DEG C -1800 DEG C, at 1680 DEG C -1750 DEG C of temperature
When stop power transmission, furnace cooling obtains U-Si compound ingot casting；
S1.3, U-Si compound ingot casting is tentatively calcined, is ground after crushing, obtains mixed-powder.
Preferably, according to centrifugal force F=m ω r2By the powder of different densities in the mixed-powder with different centrifugation rates
It is separated；Wherein m is particle effective mass, and ω is the angular speed of centrifugal rotor rotation, and r is centrifugation radius.
Preferably, the mixed-powder includes U3Si powder, U3Si2Powder and U3Si5Powder；Step S2 includes:
S2.1, the mixed-powder is poured into butterfly turntable, the butterfly turntable is with the first rotational speed omega1It is rotated,
By the maximum U of density in the mixed-powder3Si powder is thrown away to the first collector；
S2.2, to U3Si powder reduces the revolving speed of the butterfly turntable after throwing away completely, the powder of remaining different densities exists
Bisque in the butterfly turntable；
S2.3, the revolving speed of the butterfly turntable is improved to the second rotational speed omega2, by the biggish U of density in residual powder3Si2Powder
End is thrown away to the second collector；
S2.4, to U3Si2Powder reduces the revolving speed of the butterfly turntable after throwing away completely；
S2.5, the revolving speed of the butterfly turntable is improved to third rotational speed omega3, by the U in residual powder3Si5Powder throw away to
In third collector.
Preferably, the diameter of the core is 500 μm -800 μm.
Preferably, step S3 includes:
S3.1, the U that will be isolated3Si2Powder is mixed with binder, is squeezed out, is cut into short column body；
S3.2, short column body is subjected to pre-burning, makes its consistency 65%-80%T.D.；
S3.3, the short column body after pre-burning is placed in ball mill and is ground, form the smooth sphere in surface；
S3.4, sphere is sintered under reducing atmosphere, the glomerate core of shape.
Preferably, in step S4, the clad has four layers, be followed successively by from inside to outside loose buffer layer, dense barrier layer,
Structural support sealant and lubrication protection layer.
The present invention also provides a kind of inertia base dispersion fuel pellets, using made from manufacturing method described in any of the above item
High uranium density coated fuel particles are made.
The present invention also provides a kind of manufacturing methods of inertia base dispersion fuel pellet, comprising the following steps:
S1, it takes the uniform in the mixed solvent of the inertial base powder of 5-20wt.% to form slurry, and slurry is sprayed at rolling
High uranium density coated fuel particles surface, formed after slurry drying and be adhered to the powder on high uranium density coated fuel particles surface
Clad；
S2, remaining inertial base powder and the high uranium density coated fuel particles with powder clad are mixed in proportion
After conjunction, it is put into compacting in pellet mold and forms green body；
S3, the green body is subjected to vacuum non-pressure sintering densification, inertia base dispersion fuel pellet is made.
Preferably, in step S2, pressing process includes:
Oilpaper vacuum sealing is used after applying the pressure progress precompressed of 8-16MPa；
The isobaric load of 100-300MPa is applied to the vacuum-packed green body of oilpaper using cold isostatic press and pressure maintaining 1-5 divides
Clock makes green body initial density reach 50% or more.
Preferably, in step S3, vacuum non-pressure sintering densification includes:
It is that 5-20 DEG C/min/min is warming up to 500-600 DEG C with heating rate；
Apply voltage 80-150V, pulse current 3000A-5000A, in second grade process quick densifying, consistency reaches
92%-98%.
The present invention also provides a kind of integrated fuel sticks, which is characterized in that using manufacturing method described in any of the above item
High uranium density coated fuel particles obtained are made.
The present invention also provides a kind of manufacturing methods of integrated fuel stick, comprising the following steps:
S1, by high uranium density coated fuel particles and FeCrAl powder, disperse is loaded into FeCrAl involucrum after mixing
In；
S2, the eddy heating for heating generated by induction coil make FeCrAl powder be molten into liquid to 1300 DEG C -1500 DEG C
FeCrAl, the whole high uranium density coated fuel particles of submergence；
FeCrAl matrix and, the high uranium density affixed with FeCrAl involucrum are formed after S3, liquid FeCrAl cooled and solidified
Coated fuel particles are fixedly arranged in a dispersed form in FeCrAl matrix, and integrated fuel stick is made.
In the manufacturing method of high uranium density coated fuel particles of the invention, core is with UxSiy(U3Si2) be made for raw material,
Compared with UO2With high uranium density and high heat conductance, the uranium density of core material can be made to improve 17% or more, do not increasing degree of enrichment
In the case where be obviously improved the uranium loading amount of fuel.U is first prepared using smelting processxSiyPowder, then passing through powder centrifugal separation will
Different UxSiyPowder separation, obtains the higher single powder of purity, realizes continuous production；It is replaced using dry method, that is, powder metallurgic method
Sol-gal process prepares the core of coated fuel particles, reduces the pollution that chemical waste fluid generates, and simplifies operation, and reduction is prepared into
This, improves economy.
In addition, also coated fuel particles even dispersion in inertial base material and is sintered by flash burning method in the present invention
At the fuel ball or integrated fuel stick of composite construction, can be used for accident fault tolerant fuel, large-scale advanced pressurized water reactor and
The fuel system of other Advanced Nuclear Energy Systems.
Detailed description of the invention
Present invention will be further explained below with reference to the attached drawings and examples, in attached drawing:
Fig. 1 is high uranium density coated fuel particles made from high uranium density coated fuel particles manufacturing method of the invention
The schematic diagram of the section structure；
Fig. 2 is the structural schematic diagram of the inertial base dispersion fuel pellet of one embodiment of the invention.
Specific embodiment
The manufacturing method of high uranium density coated fuel particles of the invention, it may include following steps:
S1, the mixed-powder that U-Si compound is made using smelting process.
According to U-Si binary phase diagraml it is found that U-Si compound (UxSiy, x=3, y=1-5) in stable compound be U3Si、
U3Si2And U3Si5.The U-Si powder obtained under room temperature may be single compound, it is also possible to which multiple compounds coexist.
The step is made as raw material using U-Si compound (solid-state) containing there are many mixed-powders of allotrope.
Specifically, step S1 can include:
S1.1, U-Si compound is placed in vacuum melting furnace, vacuum is down to 20MPa hereinafter, power transmission, according to melting in furnace
Situation heating temperature, until U-Si compound is completely melt.
S1.2, U-Si compound are completely melt rear continuous mechanical stirring, until stopping stirring when temperature is 1500 DEG C -1800 DEG C
It mixes, stops power transmission at 1680 DEG C -1750 DEG C of temperature, furnace cooling obtains U-Si compound ingot casting.
S1.3, U-Si compound ingot casting is tentatively calcined, is ground after crushing using grinder, obtains mixed-powder.
The size controlling of mixed-powder is at 40 μm -80 μm.
It is above-mentioned that stable compound powder is prepared with smelting process, realize the industrial-scale production of raw material, while avoiding powder
The magazine or purity that end separates at high temperature and generates are inadequate, simplify technique, are conducive to high-volume and manufacture fuel core.
Mixed-powder obtained may include U3Si powder, U3Si2Powder and U3Si5Powder.The various U-Si compounds and its
Feature is as shown in table 1 below.
Table 1
| Uranium-silicon compound | Uranium density/(g/cm3) | Density/(g/cm3) | Fusing point/DEG C |
| U3Si | 14.99 | 15.58 | 930 |
| U3Si2 | 11.31 | 12.20 | 1665 |
| U3Si5 | 9.30 | 10.40 | 1600 |
As can be known from the above table, three kinds of U-Si compounds all have excellent uranium density, wherein U3The density of Si is maximum, is followed successively by
U3Si2、U3Si5。
S2, according to the difference of density between powder different in mixed-powder, using centrifugal separation by each of mixed-powder
Powder is separated.
The step is used for the U in mixed-powder3Si powder, U3Si2Powder and U3Si5Powder separation, it is higher to obtain purity
Various compound powders.
Specifically, according to centrifugal force F=m ω r2By the powder of different densities in mixed-powder with the progress of different centrifugation rates
Separation；Wherein m is particle effective mass, and ω is the angular speed of centrifugal rotor rotation, and r is centrifugation radius.
Step S2 specifically can comprise the following steps that
S2.1, mixed-powder is poured into butterfly turntable, butterfly turntable is with the first rotational speed omega1It is rotated, by mixed powder
The maximum U of density in end3Si powder is thrown away to the first collector.
S2.2, to U3Si powder reduces the revolving speed of butterfly turntable after throwing away completely, the powder of remaining different densities is in butterfly
Bisque in turntable.
First collector has collected U3After Si powder, it is changed to the second collector, to collect other lower powder of density.
S2.3, the revolving speed of butterfly turntable is improved to the second rotational speed omega2, by the biggish U of density in residual powder3Si2Powder is got rid of
Out in the second collector.
S2.4, to U3Si2Powder reduces the revolving speed of butterfly turntable after throwing away completely.
Second collector is changed to third collector, to collect subsequent other powder thrown away.
S2.5, the revolving speed of butterfly turntable is improved to third rotational speed omega3, by the U in residual powder3Si5It throws away to third and collects
In device.
Above-mentioned first rotational speed omega1, the second rotational speed omega2And third rotational speed omega3Specific value or value range according to centrifugation half
Diameter, powder particle size, turntable height etc. are configured.
To guarantee each powder purity, the corresponding revolving speed of powder is repeated, converts other turns after corresponding powder is kept completely separate
Speed.
By centrifugal separation separated powder, the allotrope of different densities is separated, having the advantages that can be continuous
Powder is produced, the industrially scalable of Yi Shixian raw material is easy to operate, convenient for control；U-Si powder is avoided to generate when separating
Impurity, it is ensured that powder purity；Be conducive to the coated fuel particles mass production of U-Si core.
S3, the U that will be isolated3Si2Powder is mixed with binder, and the smooth spherical core in surface is made.
The diameter of core is 500 μm -800 μm.
The U that above-mentioned steps S2 is separated3Si powder and U3Si5Powder can be continued for melting, powder separation, with
Obtain U3Si2Powder.
Step S3 specifically includes the following steps:
S3.1, the U that will be isolated3Si2Powder is mixed with binder, is squeezed out by pore, and short column body is cut into.
The volume of all short column bodies cut out is same or about, in order to the subsequent ball for being ground to same volume
Body.
S3.2, short column body is subjected to pre-burning, makes its consistency 65%-80%T.D..
Pre-burning uses atmosphere furnace, and the temperature of pre-burning is lower than subsequent sintering temperature.
S3.3, the short column body after pre-burning is placed in ball mill and is ground, form the smooth sphere in surface.
Concrete operations are as follows: short column body being placed in the groove of lower rotary table, groove is exposed at top；Top rotary table is cooperated to down
On turntable, grinding oil is injected therebetween, and short column body is immersed in the mixture of viscous form of diamond dust；Top rotary table and
Lower rotary table is rotated simultaneously with certain revolving speed and is turned on the contrary, short column body is made constantly to roll in the trench, and short column body is constantly and ditch
Cell wall, the top rotary table of slot contact with each other friction, and diamond dust constantly grinds off the corner of short column body, ultimately forms it with one
The sphere that scale is very little, sphericity and surface are smooth.
For the sphere of size required for obtaining, it can pass through and adjust pressure between top rotary table and lower rotary table, revolving speed, Ball-milling Time
And control presintered density etc. is realized.
S3.4, sphere is sintered under reducing atmosphere, the glomerate core of shape.
Different according to different U-Si melting point compounds, using corresponding sintering temperature, and sintering temperature slightly below corresponds to
Fusing point.
S4, it is sequentially depositing to form multilayer coating structure layer by vapour deposition process on core surface, high uranium density cladding combustion is made
Expect particle.
In the present embodiment, clad has four layers, is followed successively by loose buffer layer, dense barrier layer, structural support from inside to outside
Sealant and lubrication protection layer.
Core and the parameter of each clad are as shown in table 2 below.
Table 2
As shown in Figure 1, high uranium density coated fuel particles made from the manufacturing method of the present invention, including core 10, successively
Loose buffer layer 11, dense barrier layer 12, structural support sealant 13 and the lubrication protection layer 14 being coated on outside core 10.
It is illustrated below by way of manufacturing method of the specific embodiment to the high uranium density coated fuel particles of the present invention.
Embodiment 1
High-purity U is obtained by powder separation3Si2Powder.
Weigh a certain amount of U3Si2Powder is mixed with 2-5wt.% binder, forms dope.It will with pore extrusion die
Dope is squeezed out from pore, and formation length is the short column body of 700 ± 50nm.Pre-burning is carried out to short column body using sintering furnace, in advance
400 DEG C -600 DEG C of temperature are burnt, is cooled down after keeping the temperature 3-5h with furnace, the short column body consistency after pre-burning is 80%T.D., due to pre-burning
Temperature is lower, and bead dimensional contraction is unobvious.Short column body after pre-burning is placed in ball mill, lower rotary table is rotated, with 50r/
The revolving speed of min carries out 10-12 hour of grinding, forms bead.Bead after taking out grinding is cleaned and is screened, will be having a size of
The bead of 600 ± 50nm sifts out.It sifts out qualified bead to be sintered, using atmosphere sintering furnace, leads to H2Atmosphere, sintering temperature 1300
DEG C -1500 DEG C, sintered the small ball's diameter screens out out-of-size bead in 500 ± 50nm or so.
By way of vapor deposition outside bead wrap up 4 layers of closing spherical shell, respectively loose buffer layer, dense barrier layer,
Structural support sealant and lubrication protection layer, that is, form coated fuel particles, and cladding layer parameter is as shown in table 3 below.
Table 3
Embodiment 2
High-purity U is obtained by powder separation3Si2Powder.
Weigh a certain amount of U3Si2Powder is mixed with 2-5wt.% binder, forms dope.It will with pore extrusion die
Dope is squeezed out from pore, and formation length is the short column body of 600-700nm.Pre-burning is carried out to short column body using sintering furnace, in advance
500 ± 50 DEG C of temperature are burnt, is cooled down after keeping the temperature 2-5h with furnace, the short column body consistency after pre-burning is 80%T.D., due to pre-burning temperature
Spend lower, bead dimensional contraction is unobvious.Short column body after pre-burning is placed in ball mill, lower rotary table is rotated, with 50 ±
The revolving speed of 10r/min carries out 8-16 hour of grinding, forms bead.Bead after taking out grinding is cleaned and is screened, by ruler
The very little bead for being 600 ± 50nm sifts out.It sifts out qualified bead to be sintered, using atmosphere sintering furnace, leads to H2Atmosphere, sintering temperature
1300 DEG C -1500 DEG C, sintered the small ball's diameter screens out out-of-size bead in 500 ± 50nm or so.
By way of vapor deposition outside bead wrap up 4 layers of closing spherical shell, respectively loose buffer layer, dense barrier layer,
Structural support sealant and lubrication protection layer, that is, form coated fuel particles, and cladding layer parameter can refer to shown in above-mentioned table 3.
The inertia base dispersion fuel pellet of one embodiment of the invention, using high uranium density coated fuel particles obtained above
It is made.As shown in Fig. 2, high uranium density coated fuel particles 1 are dispersed in inertial base 2 in inertia base dispersion fuel pellet.
The manufacturing method of inertia base dispersion fuel pellet of the invention, it may include following steps:
S1, it takes and forms slurry in the uniform mixed solvent of inertial base powder (such as ethyl alcohol) of 5-20wt.%, and by pulp spraying
It is sprinkled upon the high uranium density coated fuel particles surface of rolling, is formed after slurry drying and is adhered to high uranium density coated fuel particles table
The powder clad in face.
The mode of blowing hot-air can be used in the mode of drying, and the solvent in slurry is made to volatilize.
S2, remaining inertial base powder and the high uranium density coated fuel particles with powder clad are mixed in proportion
After conjunction, it is put into compacting in pellet mold and forms green body.
When compacting, oilpaper vacuum sealing is used after first applying the pressure progress precompressed of 8-16MPa；Reuse cold isostatic press pair
The vacuum-packed green body of oilpaper applies the isobaric load of 100-300MPa and pressure maintaining 1-5 minutes, reaches green body initial density
50% or more.
S3, green body is subjected to vacuum non-pressure sintering densification, inertia base dispersion fuel pellet is made.
Wherein, vacuum non-pressure sintering, which densifies, includes:
It is that 5-20 DEG C/min is warming up to 500-800 DEG C with heating rate；The preferable 10 DEG C/min of heating rate.
Apply voltage 80-150V, pulse current 3000A-5000A, makes inertia base dispersion fuel pellet during second grade
Quick densifying, consistency reach 92% or more (92%-98%).
The integrated fuel stick of one embodiment of the invention, using high uranium density coated fuel particles system made from above-mentioned
At.In integrated fuel stick, high uranium density coated fuel particles are dispersed in FeCrAl matrix, and FeCrAl matrix is located at
In FeCrAl involucrum and with FeCrAl involucrum inner wall integrally connected.
The manufacturing method of integrated fuel stick of the invention, it may include following steps:
S1, by high uranium density coated fuel particles and FeCrAl powder, disperse is loaded into FeCrAl involucrum after mixing
In.
S2, the eddy heating for heating generated by induction coil melt FeCrAl powder to 1300 DEG C -1500 DEG C, and submergence is complete
The high uranium density coated fuel particles in portion.
The liquid FeCrAl that fusing is formed is realized and FeCrAl involucrum inner wall physical connection.FeCrAl powder is melted in heating
While, FeCrAl involucrum outer wall is implemented to force cooling, controls FeCrAl involucrum maximum temperature, makes it not due to eddy heating for heating
Lead to the annealing of performance change.
S3, the FeCrAl cooled and solidified formation FeCrAl matrix of liquid and, high uranium density cladding affixed with FeCrAl involucrum
Fuel particle is fixedly arranged in a dispersed form in FeCrAl matrix, and integrated fuel stick is made.
In inertia base dispersion fuel pellet of the invention and integrated fuel stick, inertial base and involucrum can be molten in nitric acid
Solution, realizes the recycling and fuel recycle of coated fuel particles.
The above description is only an embodiment of the present invention, is not intended to limit the scope of the invention, all to utilize this hair
Equivalent structure or equivalent flow shift made by bright specification and accompanying drawing content is applied directly or indirectly in other relevant skills
Art field, is included within the scope of the present invention.
Claims (14)
1. a kind of manufacturing method of high uranium density coated fuel particles, which comprises the following steps:
S1, the mixed-powder that U-Si compound is made using smelting process；
S2, according to the difference of density between powder different in the mixed-powder, using centrifugal separation by the mixed-powder
Each powder separated；
S3, the U that will be isolated3Si2Powder is mixed with binder, and the smooth spherical core in surface is made；
S4, it is sequentially depositing to form multilayer coating structure layer by vapour deposition process on the core surface, high uranium density cladding combustion is made
Expect particle.
2. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that in step S1,
The size controlling of the mixed-powder is at 40 μm -80 μm.
3. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that step S1 packet
It includes:
S1.1, U-Si compound is placed in vacuum melting furnace, vacuum is down to 20MPa hereinafter, power transmission, according to melting situation in furnace
Heating temperature, until U-Si compound is completely melt；
S1.2, continuous mechanical stirring stop until stopping stirring when temperature is 1500 DEG C -1800 DEG C at 1680 DEG C -1750 DEG C of temperature
Only power transmission, furnace cooling obtain U-Si compound ingot casting；
S1.3, U-Si compound ingot casting is tentatively calcined, is ground after crushing, obtains mixed-powder.
4. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that according to centrifugal force
F=mωr2The powder of different densities in the mixed-powder is separated with different centrifugation rates；Wherein m is the effective matter of particle
Amount, ω are the angular speed of centrifugal rotor rotation, and r is centrifugation radius.
5. the manufacturing method of high uranium density coated fuel particles according to claim 4, which is characterized in that the mixed powder
End includes U3Si powder, U3Si2Powder and U3Si5Powder；Step S2 includes:
S2.1, the mixed-powder is poured into butterfly turntable, the butterfly turntable is with the first rotational speed omega1It is rotated, it will be described
The maximum U of density in mixed-powder3Si powder is thrown away to the first collector；
S2.2, to U3Si powder reduces the revolving speed of the butterfly turntable after throwing away completely, the powder of remaining different densities is in the butterfly
Bisque in shape turntable；
S2.3, the revolving speed of the butterfly turntable is improved to the second rotational speed omega2, by the biggish U of density in residual powder3Si2Powder is got rid of
Out in the second collector；
S2.4, to U3Si2Powder reduces the revolving speed of the butterfly turntable after throwing away completely；
S2.5, the revolving speed of the butterfly turntable is improved to third rotational speed omega3, by the U in residual powder3Si5Powder is thrown away to third
In collector.
6. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that the core
Diameter is 500 μm -800 μm.
7. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that step S3 packet
It includes:
S3.1, the U that will be isolated3Si2Powder is mixed with binder, is squeezed out, is cut into short column body；
S3.2, short column body is subjected to pre-burning, makes its consistency 65%-80%T.D.；
S3.3, the short column body after pre-burning is placed in ball mill and is ground, form the smooth sphere in surface；
S3.4, sphere is sintered under reducing atmosphere, the glomerate core of shape.
8. the manufacturing method of high uranium density coated fuel particles according to claim 1, which is characterized in that in step S4,
The clad has four layers, is followed successively by loose buffer layer, dense barrier layer, structural support sealant and lubrication from inside to outside and protects
Sheath.
9. a kind of inertia base dispersion fuel pellet, which is characterized in that use the described in any item manufacturer's legal systems of claim 1-8
The high uranium density coated fuel particles obtained are made.
10. a kind of manufacturing method of inertia base dispersion fuel pellet as claimed in claim 9, which is characterized in that including following step
It is rapid:
S1, it takes the uniform in the mixed solvent of the inertial base powder of 5-20wt.% to form slurry, and slurry is sprayed to the height of rolling
Uranium density coated fuel particles surface forms the powder cladding for being adhered to high uranium density coated fuel particles surface after slurry drying
Layer；
S2, remaining inertial base powder is mixed in proportion with the high uranium density coated fuel particles with powder clad
Afterwards, it is put into compacting in pellet mold and forms green body；
S3, the green body is subjected to vacuum non-pressure sintering densification, inertia base dispersion fuel pellet is made.
11. the manufacturing method of inertia base dispersion fuel pellet according to claim 10, which is characterized in that in step S2,
Pressing process includes:
Oilpaper vacuum sealing is used after applying the pressure progress precompressed of 8-16MPa；
Apply isobaric load simultaneously pressure maintaining 1-5 minutes of 100-300MPa to the vacuum-packed green body of oilpaper using cold isostatic press,
Green body initial density is set to reach 50% or more.
12. the manufacturing method of inertia base dispersion fuel pellet according to claim 10, which is characterized in that in step S3,
Vacuum non-pressure sintering densifies
It is that 5-20 DEG C/min is warming up to 500-600 DEG C with heating rate；
Apply voltage 80-150V, pulse current 3000A-5000A, in second grade process quick densifying, consistency reaches 92%-
98%。
13. a kind of integrated fuel stick, which is characterized in that using made from the described in any item manufacturing methods of claim 1-8
High uranium density coated fuel particles are made.
14. the manufacturing method of integrated fuel stick described in a kind of claim 13, which comprises the following steps:
S1, by high uranium density coated fuel particles and FeCrAl powder, disperse is loaded into FeCrAl involucrum after mixing；
S2, the eddy heating for heating generated by induction coil make FeCrAl powder be molten into liquid to 1300 DEG C -1500 DEG C
FeCrAl, the whole high uranium density coated fuel particles of submergence；
FeCrAl matrix and, the high uranium density cladding affixed with FeCrAl involucrum are formed after S3, liquid FeCrAl cooled and solidified
Fuel particle is fixedly arranged in a dispersed form in FeCrAl matrix, and integrated fuel stick is made.
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Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110853769A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Pellet fuel core, fuel rod and small-size reactor of metal cooling |
| CN110993134A (en) * | 2019-11-12 | 2020-04-10 | 中国工程物理研究院材料研究所 | U-shaped connector3Si2Preparation method of alloy fuel |
| CN111195606A (en) * | 2019-12-26 | 2020-05-26 | 岭东核电有限公司 | Method for separating triuranium silicon in uranium silicide smelting body and nuclear fuel pellet |
| CN111508628A (en) * | 2020-04-17 | 2020-08-07 | 中国科学院合肥物质科学研究院 | Preparation method of tungsten or molybdenum-based fuel pellet with uranium dioxide core balls dispersed and distributed |
| CN112242203A (en) * | 2020-10-19 | 2021-01-19 | 中国核动力研究设计院 | Component grid arrangement form for loading FCM fuel |
| CN112678872A (en) * | 2020-11-20 | 2021-04-20 | 中核北方核燃料元件有限公司 | Method for recycling uranium in spherical fuel element |
| CN112992390A (en) * | 2021-02-25 | 2021-06-18 | 上海核工程研究设计院有限公司 | High-safety uranium silicide composite fuel pellet |
| CN113012834A (en) * | 2019-12-20 | 2021-06-22 | 中核北方核燃料元件有限公司 | Preparation method of uranium nitride composite uranium trisilicon two-fuel pellet |
| CN113816749A (en) * | 2021-10-21 | 2021-12-21 | 中国科学院上海应用物理研究所 | High-density U3Si2Method for producing fuel |
| WO2023130356A1 (en) * | 2022-01-07 | 2023-07-13 | 岭澳核电有限公司 | High-uranium-density atf nuclear fuel pellet and preparation method therefor |
Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006234405A (en) * | 2005-02-22 | 2006-09-07 | Nuclear Fuel Ind Ltd | Clad fuel particle, overcoat particles and method of manufacturing same |
| US20110091004A1 (en) * | 2007-10-04 | 2011-04-21 | Lawrence Livermore National Security, Llc | Triso fuel for high burn-up nuclear engine |
| US20160372221A1 (en) * | 2015-06-22 | 2016-12-22 | Battelle Energy Alliance, Llc. | Methods of forming triuranium disilicide structures, and related fuel rods for light water reactors |
| CN106981318A (en) * | 2017-04-13 | 2017-07-25 | 中国工程物理研究院材料研究所 | A kind of inertia base disperse pellet fuel and its production and use |
| CN107093468A (en) * | 2017-05-27 | 2017-08-25 | 中国工程物理研究院材料研究所 | A kind of ZrC inertia base disperse pellet nuclear fuel and its preparation method and purposes |
| CN107180654A (en) * | 2017-05-27 | 2017-09-19 | 中国工程物理研究院材料研究所 | A kind of MAX phase ceramics matrix disperse pellet nuclear fuel and its preparation method and purposes |
| US20170278586A1 (en) * | 2015-02-19 | 2017-09-28 | X-Energy, Llc | Nuclear fuel pebble and method of manufacturing the same |
| CN108335760A (en) * | 2018-02-01 | 2018-07-27 | 中国工程物理研究院材料研究所 | A kind of preparation method of high uranium useful load dispersion fuel pellet |
| CN109326363A (en) * | 2018-09-29 | 2019-02-12 | 中广核研究院有限公司 | Diffusion-type fuel pellet and preparation method thereof, fuel rod |
| CN109461509A (en) * | 2018-09-29 | 2019-03-12 | 中广核研究院有限公司 | Inertial base dispersion fuel pellet and preparation method thereof |
| CN109594017A (en) * | 2018-11-27 | 2019-04-09 | 中国科学院金属研究所 | A kind of preparation method of oxide dispersion intensifying FeCrAl alloy pipe |
-
2019
- 2019-05-07 CN CN201910377421.9A patent/CN110223789B/en active Active
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006234405A (en) * | 2005-02-22 | 2006-09-07 | Nuclear Fuel Ind Ltd | Clad fuel particle, overcoat particles and method of manufacturing same |
| US20110091004A1 (en) * | 2007-10-04 | 2011-04-21 | Lawrence Livermore National Security, Llc | Triso fuel for high burn-up nuclear engine |
| US20170278586A1 (en) * | 2015-02-19 | 2017-09-28 | X-Energy, Llc | Nuclear fuel pebble and method of manufacturing the same |
| US20160372221A1 (en) * | 2015-06-22 | 2016-12-22 | Battelle Energy Alliance, Llc. | Methods of forming triuranium disilicide structures, and related fuel rods for light water reactors |
| CN106981318A (en) * | 2017-04-13 | 2017-07-25 | 中国工程物理研究院材料研究所 | A kind of inertia base disperse pellet fuel and its production and use |
| CN107093468A (en) * | 2017-05-27 | 2017-08-25 | 中国工程物理研究院材料研究所 | A kind of ZrC inertia base disperse pellet nuclear fuel and its preparation method and purposes |
| CN107180654A (en) * | 2017-05-27 | 2017-09-19 | 中国工程物理研究院材料研究所 | A kind of MAX phase ceramics matrix disperse pellet nuclear fuel and its preparation method and purposes |
| CN108335760A (en) * | 2018-02-01 | 2018-07-27 | 中国工程物理研究院材料研究所 | A kind of preparation method of high uranium useful load dispersion fuel pellet |
| CN109326363A (en) * | 2018-09-29 | 2019-02-12 | 中广核研究院有限公司 | Diffusion-type fuel pellet and preparation method thereof, fuel rod |
| CN109461509A (en) * | 2018-09-29 | 2019-03-12 | 中广核研究院有限公司 | Inertial base dispersion fuel pellet and preparation method thereof |
| CN109594017A (en) * | 2018-11-27 | 2019-04-09 | 中国科学院金属研究所 | A kind of preparation method of oxide dispersion intensifying FeCrAl alloy pipe |
Non-Patent Citations (2)
| Title |
|---|
| 张翔 等: "U_3Si_2燃料芯块的制备与显微组织研究", 《核动力工程》 * |
| 陶小康 等: "新型轻水反应堆包壳材料FeCrAl合金的研究进展", 《热加工工艺》 * |
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110993134B (en) * | 2019-11-12 | 2023-01-06 | 中国工程物理研究院材料研究所 | U-shaped connector 3 Si 2 Preparation method of alloy fuel |
| CN110993134A (en) * | 2019-11-12 | 2020-04-10 | 中国工程物理研究院材料研究所 | U-shaped connector3Si2Preparation method of alloy fuel |
| CN110853769A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Pellet fuel core, fuel rod and small-size reactor of metal cooling |
| CN113012834A (en) * | 2019-12-20 | 2021-06-22 | 中核北方核燃料元件有限公司 | Preparation method of uranium nitride composite uranium trisilicon two-fuel pellet |
| CN111195606A (en) * | 2019-12-26 | 2020-05-26 | 岭东核电有限公司 | Method for separating triuranium silicon in uranium silicide smelting body and nuclear fuel pellet |
| CN111195606B (en) * | 2019-12-26 | 2021-11-09 | 岭东核电有限公司 | Method for separating triuranium silicon in uranium silicide smelting body and nuclear fuel pellet |
| CN111508628A (en) * | 2020-04-17 | 2020-08-07 | 中国科学院合肥物质科学研究院 | Preparation method of tungsten or molybdenum-based fuel pellet with uranium dioxide core balls dispersed and distributed |
| CN112242203A (en) * | 2020-10-19 | 2021-01-19 | 中国核动力研究设计院 | Component grid arrangement form for loading FCM fuel |
| CN112678872A (en) * | 2020-11-20 | 2021-04-20 | 中核北方核燃料元件有限公司 | Method for recycling uranium in spherical fuel element |
| CN112992390A (en) * | 2021-02-25 | 2021-06-18 | 上海核工程研究设计院有限公司 | High-safety uranium silicide composite fuel pellet |
| CN113816749A (en) * | 2021-10-21 | 2021-12-21 | 中国科学院上海应用物理研究所 | High-density U3Si2Method for producing fuel |
| CN113816749B (en) * | 2021-10-21 | 2023-02-17 | 中国科学院上海应用物理研究所 | High-density U 3 Si 2 Method for producing fuel |
| WO2023130356A1 (en) * | 2022-01-07 | 2023-07-13 | 岭澳核电有限公司 | High-uranium-density atf nuclear fuel pellet and preparation method therefor |
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