CN106971765A - A kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet - Google Patents
A kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet Download PDFInfo
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- CN106971765A CN106971765A CN201710238535.6A CN201710238535A CN106971765A CN 106971765 A CN106971765 A CN 106971765A CN 201710238535 A CN201710238535 A CN 201710238535A CN 106971765 A CN106971765 A CN 106971765A
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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
- 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
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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
- 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
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Abstract
The invention discloses a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet, including prepare mixed slurry, prepare core-shell structure particles, compacting core, compacting nucleocapsid and prepare shape this five steps.The preparation method overcomes the problem of existing inertia base dispersion fuel pellet TRISO contents are low, can compared with obtaining that TRISO granule contents are high, granule integrity is good in the short processes cycle, be uniformly dispersed and inertia base dispersion fuel pellet that silicon carbide substrate consistency is high.In the inertia base dispersion fuel pellet being prepared from, silicon carbide substrate consistency reaches that volume fraction content of more than 92%, the TRISO particles in fuel entirety can reach 30% ~ 65%.
Description
Technical field
The present invention relates to the preparation method for being related to ceramic mould nuclear fuel, and in particular to a kind of high TRISO contents inertia base is more
Dissipate the preparation technology of fuel pellet.
Background technology
Along with the high speed development of industrial level, rapid growth is also presented in AND ENERGY RESOURCES CONSUMPTION IN CHINA.To the serious of thermal power generation
Dependence causes China in reduction of greenhouse gas discharge and ensures to face significant challenge on energy sustainable supply.Nuclear power is used as a kind of technology
The clean energy resource Land use systems that ripe, security is improved constantly, it is close with capacity factor measure height, energy compared with wind-powered electricity generation, solar energy
Degree is big, good economy performance, specific investment cost emission reduction high efficiency the advantages of.Nuclear Power Development is economical for adjustment China energy resource structure, promotion
There is important strategic importance with social sustainable development.However, the intrinsic small probability of nuclear power itself, the security lost greatly are asked
Topic turns into the biggest factor for hindering nuclear power developing.After Fukushima, Japan nuclear accident, countries in the world start to pay high attention to nuclear fuel member
Part security.New accident fault-tolerant nuclear fuel of the exploitation with high intrinsic safety, is remarkably improved nuclear fuel assembly and core
The security in power station, is prevented effectively from the generation that Nuclear Power Accident, particularly radioactive substance leak nuclear accident.
Inertia base dispersion fuel pellet is the structure design for using for reference HTGR nuclear fuel, by traditional uranium dioxide system
It is made the three structure isotropism particles for being carbonized silicon and carbon multilayer coating structure（TRISO）, then disperseed to be sealed to ceramic material
Novel combined nuclear fuel of the TRISO disperses in inactive ceramic matrix is formed in matrix.Relative to traditional pure uranium dioxide
Fuel pellet, inertia base dispersion fuel pellet utilizes the spies such as ceramic material excellent heat conductivility, high-temperature stability, inoxidizability
Point improves the thermal conductivity of fuel pellet and takes performance in fission gaseous products, effectively under delay major accident operating mode, combustion
Material DIE Temperature steeply rises, and reactor core melts down, and zirconium water reactive hydrogen is quick-fried, the calamitous nuclear accident such as radioactive substance leakage occur when
Between, so as to greatly improve the essential safety performance of fuel assembly and nuclear reactor.
Current inertia base dispersion fuel pellet, as ceramic matrix, passes through high warm using carborundum after both are mixed
Reaction sintering technology is pressed to prepare, not only high to equipment requirement, production cycle length, efficiency are low, cost is high, and TRISO particles are in carbon
Dispersion effect in SiClx matrix is poor, it is difficult to realize industrialization.Importantly, in order to avoid TRISO particles are in high temperature pressure
The radioactive substance for crushing and causing under effect is exposed, the volume fraction content one of the TRISO particles added in silicon carbide substrate
As be no more than 40%, in order to avoid top layer TRISO Particle Breakages and putting for causing during peripheral milling processing is carried out to fuel
Penetrating property material is exposed, needs one layer of increase to have certain thickness carborundum without fuel region protective layer outside fuel core, therefore
TRISO grain volume fractions content not more than 40% in the inertia base dispersion fuel pellet, due to TRSIO itself structure
It is uranium dioxide fuel there was only about eighth volume in feature, whole particle, therefore the overall uranium loading amount of fuel pellet is very
Low, economy is very poor, it is difficult to meet the use requirement of commercial presurized water reactor at present.
The content of the invention
The invention aims to overcome above-mentioned technical problem, there is provided a kind of high TRISO contents inertia base dispersion fuel
The preparation method of pellet, this method can prepare that TRISO granule contents are high, granule integrity is good within compared with the short processes cycle,
It is uniformly dispersed, the high inertia base dispersion fuel pellet of silicon carbide substrate consistency.
To achieve the above object, the technical solution adopted by the present invention is as follows：
A kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet, comprises the following steps：
（1）Prepare mixed slurry：First by weight percentage, it is 0 ~ 15% sintering aid and 85 ~ 100% silicon carbide powder is logical
Overly moist miscible agent carries out wet mixing mixing, and then addition accounts for sintering aid and point of silicon carbide powder gross mass 0.5 ~ 3% thereto again
Powder, 4 ~ 24h of stirring is sufficiently mixed it, obtains finely dispersed carborundum mixed slurry；
（2）Prepare core-shell structure particles：TRISO particles are fitted into heatable roller, roller are opened, and be heated temperature
Control makes TRISO particles be rolled in roller, after TRISO particle temperatures rise to 60 ~ 90 DEG C, sprayed with air pressure at 60 ~ 90 DEG C
Mist device is by step（1）In obtain partial blend slurry atomization after continuous spray to TRISO particle surfaces, with mixed slurry
In wet mixing solvent volatilized rapidly at a temperature of 60 ~ 90 DEG C, can on TRISO particles formed one layer of carborundum clad, i.e.,
The TRISO/SiC core-shell structure particles containing uranium dioxide can be obtained；
（3）Suppress core：By step（2）In the box shell grains that the prepare die forming under 10 ~ 80MPa pressure, obtain
The core for the cylindrical inertia base dispersion fuel pellet for being to a diameter of 6 ~ 8mm, highly 12 ~ 14.5mm；
（4）Suppress nucleocapsid：It is that 6.2 ~ 8.2mm, external diameter are 8.2 ~ 9mm, are highly 12 ~ 14.5mm and and step to take internal diameter（3）In
The silicon carbide fibre pipe that matches of core, and a diameter of 8.2 ~ 9mm, thickness by 0.4mm and with the silicon carbide fibre that takes
The silicon carbide fibre disk that pipe both ends of the surface match, and by above-mentioned silicon carbide fibre pipe and silicon carbide fibre disk in step
（1）In vacuum impregnation 30min in obtained carborundum mixed slurry, then take out drying；Wherein, vacuum-impregnated vacuum
For -0.1MPa；
（5）Prepare shaping：The core of cylindrical inertia base dispersion fuel pellet is loaded in silicon carbide fibre pipe, and by carborundum
Fiber disk is covered in behind silicon carbide fibre pipe upper and lower end face, overall to carry out discharge plasma sintering, and sintering temperature is 1600 ~
2000 DEG C, reach that it is 10 ~ 50MPa that sintering pressure is adjusted after sintering temperature, then be incubated 5 ~ 20min, be subsequently cooled to room temperature, you can
Obtain the inertia base dispersion fuel pellet of high TRISO contents.
Specifically, the step（1）In sintering aid particle diameter be 20nm ~ 50 μm, the sintering aid for oxidation
One or more in aluminium, yittrium oxide and silica.
Specifically, the step（1）In silicon carbide powder particle diameter be 20nm ~ 50 μm.
Specifically, the step（1）In wet mixing solvent be absolute ethyl alcohol or acetone.
Specifically, the step（1）Middle dispersant is polyethyleneimine.
Further, the step（2）In TRISO particles be a kind of spherical of standard type nuclear fuel containing uranium dioxide
Grain, the structure isotropism of particle three, a diameter of 0.8 ~ 1.0mm.
It is preferred that, the step（2）In carborundum clad weight be TRISO particle own wts 60 ~ 265%.
Further, the step（2）In, can be by controlling air-blast atomizing device spray time to control carborundum to coat
The thickness and weight of layer.
Compared with prior art, the invention has the advantages that：
（1）The present invention is that the core-shell structure particles that carborundum coats TRISO particles are prepared using spray deposition technique, is used
The silicon carbide micro-powder of nanometer to micron grain size can be uniformly coated on TRISO particle surfaces, coated particle by spray deposition technique
Good sphericity, coating thickness is controllable, difficult for drop-off, it is ensured that the TRISO particles of big particle diameter are in nanometer and micron order carborundum
Being uniformly distributed in matrix；Avoid the breakage of TRISO particles in preparation process；Silicon carbide substrate is improved to take fission product in
Performance；Improve pellet internal stress distribution uniformity under high temperature；Improve content and pellet of the TRISO particles in silicon carbide substrate
Overall uranium loading amount, so as to ensure the security and economy of inertia base dispersion fuel pellet.
（2）The present invention using match with core and the silicon carbide fibre pipe after carborundum mixed slurry impregnation process and
Fiber disk is coated and combined sintering to inertia base dispersion fuel pellet core, in fuel after sintered and simple machining
Core external forms one layer of very thin compact silicon carbide without fuel region protective layer, not only can further improve fuel pellet overall
Thermal conductivity, can also realize fuel core and external environment condition it is completely isolated on the premise of reduce no fuel region to greatest extent and exist
Shared volume fraction in pellet, not only improves fuel pellet to the performance of taking in of fission product, more greatly improved in pellet
The content and uranium loading amount of TRISO particles, so as to significantly improve the security and economy of inertia base dispersion fuel pellet；
（3）The present invention realizes inertia base dispersion fuel pellet core with carborundum without fuel using discharge plasma sintering technology
The integrated Fast Sintering and shaping technology of preparing in area, sintering temperature is low, pressure is low, the time is short, and not only fuel pellet prepares week
Phase more conventional method shortens more than 10 times, can also be prevented effectively from pellet TRISO particles and silicon carbide substrate at high temperature not
Good reaction, it is to avoid breakage of the TRISO particles in pressure sintering process, suppresses the growth of carborundum grain, improves silicon carbide-based
The consistency of body, improves the overall uranium loading amount of content and pellet of the TRISO particles in silicon carbide substrate, so as to greatly improve lazy
The overall performance of property base dispersion fuel pellet.
（4）In the inertia base dispersion fuel pellet that the present invention is prepared from, silicon carbide substrate consistency reaches more than 92%,
After cylindrical centerless break-in end face plain grinding, volume fraction content of the TRISO particles in fuel entirety can reach 30% ~ 65%.
Brief description of the drawings
Fig. 1 is preparation technology block diagram of the invention.
Distribution schematic diagrams of the Fig. 2 for TRISO particles of the invention in silicon carbide substrate.
Fig. 3 is close arrangement and interfacial structure scanning schematic diagram of the TRISO particles in silicon carbide substrate.
Embodiment
The invention will be further described with embodiment for explanation below in conjunction with the accompanying drawings, and mode of the invention includes but not only limited
In following examples.
The purpose of following examples is to overcome the shortcomings of that existing inertia base dispersion fuel pellet preparation method is present, carry
For a kind of preparation method of high TRISO contents inertia base dispersion fuel pellet, this method can be obtained compared with the short processes cycle
TRISO granule contents are high, granule integrity is good, be uniformly dispersed and inertia base dispersion fuel core that silicon carbide substrate consistency is high
Block.As shown in figure 1, following examples include preparing mixed slurry → prepare core-shell structure particles → compacting core → compacting core
Shell → preparation shapes this five steps, and the embodiment of each embodiment is as follows：
Embodiment 2
（1）Prepare mixed slurry：By weight percentage, by 5% alumina powder, 3% oxidation yttrium powder, 2% silicon dioxide powder and
90% carborundum powder carries out wet mixing mixing by wet mixing solvent of propyl alcohol, and then addition accounts for sintering aid and carborundum thereto again
The polyethyleneimine of powder gross mass 3% is as dispersant, and stirring 4h makes after it is sufficiently mixed, to obtain finely dispersed carborundum
Mixed slurry；
（2）Prepare core-shell structure particles：By the standard type nuclear fuel spherical particle containing uranium dioxide（Three structure isotropism
Grain）And a diameter of 0.8 ~ 1.0mm TRISO particles are fitted into heatable roller, roller is opened, and be heated temperature control
At 60 DEG C, TRISO particles are made to be rolled in roller, after TRISO particle temperatures rise to 60 DEG C, by sprayed deposit by step
（1）In obtain partial blend slurry atomization after continuous spray to TRISO particle surfaces, with the wet mixing solvent in mixed slurry
Volatilized rapidly at a temperature of 60 DEG C, one layer of carborundum clad is formed on TRISO particles, so as to obtain containing uranium dioxide
TRISO/SiC core-shell structure particles, the core-shell structure particles increase weight 60% on the basis of TRISO particles；
（3）Suppress core：By step（2）In the core-shell structure particles that prepare be fitted into powder metallurgy die, in 20MPa pressures
Be pressed under power a diameter of 8mm, highly for 14.5mm cylindrical inertia base dispersion fuel pellet core；
（4）Suppress nucleocapsid：It is that 8.2mm, external diameter are 9mm, are highly 14.5mm silicon carbide fibre pipe to take internal diameter, and a diameter of
9mm, thickness are 0.4mm silicon carbide fibre disk, and by the silicon carbide fibre pipe and silicon carbide fibre disk of taking-up in step
Suddenly（1）In carry out vacuum impregnation 30min in obtained carborundum mixed slurry, then take out drying；Wherein, it is vacuum-impregnated true
Reciprocal of duty cycle is -0.1MPa；
（5）Prepare shaping：The core of cylindrical inertia base dispersion fuel pellet is loaded in silicon carbide fibre pipe, and by carborundum
Fiber disk is covered in behind silicon carbide fibre pipe upper and lower end face, overall to be fitted into discharge plasma sintering special graphite mould
Row discharge plasma is sintered, and sintering temperature is 1750 DEG C, reaches that it is 20MPa that sintering pressure is adjusted after sintering temperature, then be incubated
20min, then cools to room temperature with the furnace, obtains inertia base dispersion fuel pellet, the inertia base dispersion fuel pellet silicon carbide substrate
Consistency reaches that more than 97.1%, TRISO grain structures are complete, be uniformly dispersed and volume fraction content is up to 64.8%.
Embodiment 3
（1）Prepare mixed slurry：By weight percentage, by 7.5% alumina powder, 4.5% oxidation yttrium powder, 3% silica
Powder and 85% carborundum powder carry out wet mixing mixing by wet mixing solvent of absolute ethyl alcohol, and then addition accounts for sintering aid thereto again
With the polyethyleneimine of silicon carbide powder gross mass 0.5% as dispersant, stirring 16h makes after it is sufficiently mixed, to obtain scattered equal
Even carborundum mixed slurry；
（2）Prepare core-shell structure particles：By the standard type nuclear fuel spherical particle containing uranium dioxide（Three structure isotropism
Grain）And a diameter of 0.8 ~ 1.0mm TRISO particles are fitted into heatable roller, roller is opened, and be heated temperature control
At 90 DEG C, TRISO particles is rolled in roller, after TRISO particle temperatures rise to 90 DEG C, will be walked with air-blast atomizing device
Suddenly（1）In obtain partial blend slurry atomization after continuous spray to TRISO particle surfaces, as the wet mixing in mixed slurry is molten
Agent is volatilized rapidly at a temperature of 90 DEG C, one layer of carborundum clad is formed on TRISO particles, so as to obtain containing uranium dioxide
TRISO/SiC core-shell structure particles, the core-shell structure particles increase weight 110% on the basis of TRISO particles；
（3）Suppress core：By step（2）In the core-shell structure particles that prepare be fitted into powder metallurgy die, in 40MPa pressures
Be pressed under power a diameter of 8mm, highly for 14mm cylindrical inertia base dispersion fuel pellet core；
（4）Suppress nucleocapsid：It is that 8.2mm, external diameter are 9mm, are highly 14mm silicon carbide fibre pipe to take internal diameter, and a diameter of
9mm, thickness are 0.4mm silicon carbide fibre disk, and by the silicon carbide fibre pipe and silicon carbide fibre disk of taking-up in step
Suddenly（1）In carry out vacuum impregnation 30min in obtained carborundum mixed slurry, then take out drying；Wherein, it is vacuum-impregnated true
Reciprocal of duty cycle is -0.1MPa；
（5）Prepare shaping：The core of cylindrical inertia base dispersion fuel pellet is loaded in silicon carbide fibre pipe, and by carborundum
Fiber disk is covered in behind silicon carbide fibre pipe upper and lower end face, overall to be fitted into discharge plasma sintering special graphite mould
Row discharge plasma is sintered, and sintering temperature is 1600 DEG C, and adjustment sintering pressure is 10MPa after sintering temperature to be achieved, then is protected
Warm 10min, then cools to room temperature with the furnace, obtains inertia base dispersion fuel pellet, and the inertia base dispersion fuel pellet is silicon carbide-based
Body consistency reaches that more than 97.3%, TRISO grain structures are complete, be uniformly dispersed and volume fraction content is up to 49.5%.
Embodiment 4
（1）Prepare mixed slurry：By weight percentage, by 4% alumina powder, 2.4% oxidation yttrium powder, 1.6% silica
Powder and 92% carborundum powder carry out wet mixing mixing by wet mixing solvent of absolute ethyl alcohol, and then addition accounts for sintering aid thereto again
With the polyethyleneimine of silicon carbide powder gross mass 2% as dispersant, stirring 12h makes after it is sufficiently mixed, to be uniformly dispersed
Carborundum mixed slurry；
（2）Prepare core-shell structure particles：By the standard type nuclear fuel spherical particle containing uranium dioxide（Three structure isotropism
Grain）And a diameter of 0.8 ~ 1.0mm TRISO particles are fitted into heatable roller, roller is opened, and be heated temperature control
At 80 DEG C, TRISO particles is rolled in roller, after TRISO particle temperatures rise to 80 DEG C, will be walked with air-blast atomizing device
Suddenly（1）In obtain partial blend slurry atomization after continuous spray to TRISO particle surfaces, as the wet mixing in mixed slurry is molten
Agent is volatilized rapidly at a temperature of 80 DEG C, one layer of carborundum clad is formed on TRISO particles, so as to obtain containing uranium dioxide
TRISO/SiC core-shell structure particles, the core-shell structure particles increase weight 265% on the basis of TRISO particles；
（3）Suppress core：By step（2）In the core-shell structure particles that prepare be fitted into powder metallurgy die, 10 ~
Be pressed under 80MPa pressure a diameter of 6mm, highly for 12.5mm cylindrical inertia base dispersion fuel pellet core；
（4）Suppress nucleocapsid：It is that 6.2mm, external diameter are 8.2mm, are highly 12.5mm silicon carbide fibre pipe to take internal diameter, and diameter
The silicon carbide fibre disk for being 0.4mm for 8.2mm, thickness, and the silicon carbide fibre pipe and silicon carbide fibre disk of taking-up is equal
In step（1）In carry out vacuum impregnation 30min in obtained carborundum mixed slurry, then take out drying；Wherein, vacuum impregnation
Vacuum be -0.1MPa；
（5）Prepare shaping：The core of cylindrical inertia base dispersion fuel pellet is loaded in silicon carbide fibre pipe, and by carborundum
Fiber disk is covered in behind silicon carbide fibre pipe upper and lower end face, overall to be fitted into discharge plasma sintering special graphite mould
Row discharge plasma is sintered, and sintering temperature is 1850 DEG C, and adjustment sintering pressure is 50MPa after sintering temperature to be achieved, then is protected
Warm 5min, then cools to room temperature with the furnace, obtains inertia base dispersion fuel pellet, the inertia base dispersion fuel pellet silicon carbide substrate
Consistency reaches that more than 96.4%, TRISO grain structures are complete, be uniformly dispersed and volume fraction content is up to 29.7%.
From above-described embodiment and Fig. 2 and Fig. 3, the quick preparation technology of the inertia base dispersion fuel pellet of the present embodiment
Low for equipment requirements and with short production cycle, efficiency high, TRISO particles are wrapped in carborundum, it is ensured that TRISO particles
Integrality；And be enclosed with the outside of the TRISO particles of carborundum and be also enclosed with silicon carbide fibre nucleocapsid, TRISO can be prevented effectively from
The volume fraction content of grain more than 40% after because high temperature pressure effect is lower broken and caused by radioactive substance it is exposed the problem of；Therefore,
The characteristics of uranium loading amount with TRISO grain volume fractions content height, fuel pellet entirety is high, can meet commercial presurized water reactor at present
Use requirement.
Above-described embodiment is only the preferred embodiment of the present invention, should not be taken to limit protection scope of the present invention, but
It is all the present invention body design thought and mentally make have no the change of essential meaning or polishing, its technology solved
Problem is still consistent with the present invention, should be included within protection scope of the present invention.
Claims (8)
1. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet, it is characterised in that comprise the following steps：
（1）Prepare mixed slurry：First by weight percentage, it is 0 ~ 15% sintering aid and 85 ~ 100% silicon carbide powder is logical
Overly moist miscible agent carries out wet mixing mixing, and then addition accounts for sintering aid and point of silicon carbide powder gross mass 0.5 ~ 3% thereto again
Powder, 4 ~ 24h of stirring is sufficiently mixed it, obtains finely dispersed carborundum mixed slurry；
（2）Prepare core-shell structure particles：TRISO particles are fitted into heatable roller, roller are opened, and be heated temperature
Control makes TRISO particles be rolled in roller, after TRISO particle temperatures rise to 60 ~ 90 DEG C, sprayed with air pressure at 60 ~ 90 DEG C
Mist device is by step（1）In obtain partial blend slurry atomization after continuous spray to TRISO particle surfaces, with mixed slurry
In wet mixing solvent volatilized rapidly at a temperature of 60 ~ 90 DEG C, can on TRISO particles formed one layer of carborundum clad, i.e.,
The TRISO/SiC core-shell structure particles containing uranium dioxide can be obtained；
（3）Suppress core：By step（2）In the box shell particle that the prepares die forming under 10 ~ 80MPa pressure, obtain straight
Footpath is 6 ~ 8mm, be highly 12 ~ 14.5mm cylindrical inertia base dispersion fuel pellet core；
（4）Suppress nucleocapsid：It is that 6.2 ~ 8.2mm, external diameter are 8.2 ~ 9mm, are highly 12 ~ 14.5mm and and step to take internal diameter（3）In
The silicon carbide fibre pipe that matches of core, and a diameter of 8.2 ~ 9mm, thickness by 0.4mm and with the silicon carbide fibre that takes
The silicon carbide fibre disk that pipe both ends of the surface match, and by above-mentioned silicon carbide fibre pipe and silicon carbide fibre disk in step
（1）In vacuum impregnation 30min in obtained carborundum mixed slurry, then take out drying；Wherein, vacuum-impregnated vacuum
For -0.1MPa；
（5）Prepare shaping：The core of cylindrical inertia base dispersion fuel pellet is loaded in silicon carbide fibre pipe, and by carborundum
Fiber disk is covered in behind silicon carbide fibre pipe upper and lower end face, overall to carry out discharge plasma sintering, and sintering temperature is 1600 ~
2000 DEG C, reach that it is 10 ~ 50MPa that sintering pressure is adjusted after sintering temperature, then be incubated 5 ~ 20min, be subsequently cooled to room temperature, you can
Obtain the inertia base dispersion fuel pellet of high TRISO contents.
2. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 1, its feature exists
In the step（1）In sintering aid particle diameter be 20nm ~ 50 μm, the sintering aid be aluminum oxide, yittrium oxide and dioxy
One or more in SiClx.
3. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 1, its feature exists
In the step（1）In silicon carbide powder particle diameter be 20nm ~ 50 μm.
4. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 1, its feature exists
In the step（1）In wet mixing solvent be absolute ethyl alcohol or acetone.
5. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 1, its feature exists
In the step（1）Middle dispersant is polyethyleneimine.
6. a kind of preparation work of high TRISO contents inertia base dispersion fuel pellet according to claim 1 ~ 5 any one
Skill, it is characterised in that the step（2）In TRISO particles be a kind of standard type nuclear fuel spherical particle containing uranium dioxide,
The structure isotropism of particle three, a diameter of 0.8 ~ 1.0mm.
7. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 6, its feature exists
In the step（2）In carborundum clad weight be TRISO particle own wts 60 ~ 265%.
8. a kind of preparation technology of high TRISO contents inertia base dispersion fuel pellet according to claim 6, its feature exists
In the step（2）In, the thickness and again of carborundum clad can be controlled by controlling air-blast atomizing device spray time
Amount.
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| CN107967950A (en) * | 2017-11-01 | 2018-04-27 | 中广核研究院有限公司 | The manufacture method and fuel pellet of fuel pellet |
| CN108249925A (en) * | 2017-12-20 | 2018-07-06 | 中核北方核燃料元件有限公司 | A kind of preparation method of complete ceramic microencapsulated fuel pellet |
| CN108806804A (en) * | 2018-05-28 | 2018-11-13 | 广东核电合营有限公司 | Fibre-reinforced fuel pellets of SiC and preparation method thereof |
| CN109979610A (en) * | 2019-02-28 | 2019-07-05 | 中国工程物理研究院材料研究所 | A kind of double elements is co-doped with the enhanced uranium dioxide pellet of heating power and preparation method |
| CN109994223A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | A kind of novel dispersion fuel and its manufacturing method |
| 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 |
| CN113611435A (en) * | 2021-08-17 | 2021-11-05 | 西北工业大学 | Ceramic composite fuel pellet and preparation method and application thereof |
| CN113658724A (en) * | 2021-08-17 | 2021-11-16 | 西北工业大学 | Ceramic composite fuel pellet and preparation method and application thereof |
| WO2023029317A1 (en) * | 2021-09-02 | 2023-03-09 | 中国核电工程有限公司 | Homogenized coated particle dispersion fuel and preparation method theref |
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| CN107967950A (en) * | 2017-11-01 | 2018-04-27 | 中广核研究院有限公司 | The manufacture method and fuel pellet of fuel pellet |
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| CN109979610A (en) * | 2019-02-28 | 2019-07-05 | 中国工程物理研究院材料研究所 | A kind of double elements is co-doped with the enhanced uranium dioxide pellet of heating power and preparation method |
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| 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 |
| CN113611435A (en) * | 2021-08-17 | 2021-11-05 | 西北工业大学 | Ceramic composite fuel pellet and preparation method and application thereof |
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| WO2023029317A1 (en) * | 2021-09-02 | 2023-03-09 | 中国核电工程有限公司 | Homogenized coated particle dispersion fuel and preparation method theref |
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