CN107256726A - A kind of preparation method of metal reinforced uranium dioxide fuel ball - Google Patents
A kind of preparation method of metal reinforced uranium dioxide fuel ball Download PDFInfo
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- CN107256726A CN107256726A CN201710533031.7A CN201710533031A CN107256726A CN 107256726 A CN107256726 A CN 107256726A CN 201710533031 A CN201710533031 A CN 201710533031A CN 107256726 A CN107256726 A CN 107256726A
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- uranium dioxide
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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
- G21C3/62—Ceramic fuel
- G21C3/64—Ceramic dispersion fuel, e.g. cermet
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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
Abstract
The invention discloses a kind of preparation method of metal reinforced uranium dioxide fuel ball.The preparation method mainly includes two big steps, and one is to prepare core-shell structure particles, i.e., sintered using discharge plasma（Spark Plasma Sintering,SPS）Technology is to UO2Powder carries out the quick pre-burning of low temperature, and UO is obtained after granulation, nodularization2Bead, then with metal（One of Mo, Cr, W etc.）Micro mist carries out the mode of physical mixed, and metal fine powder is coated into UO2 bead surfaces, the core-shell structure particles of metallic cover uranium dioxide are made；Two be to prepare fuel ball, i.e., using being coated on UO2After the metal dust High-temperature Liquefaction of bead surface, in UO2The micro-cell structure continuous phase similar to membrane structure is formed around bead, with UO2Matrix forms special metal reinforced UO2Fuel ball.
Description
Technical field
The present invention relates to nuclear fuel field, and in particular to a kind of preparation side of metal reinforced uranium dioxide fuel ball
Method.
Background technology
Uranium dioxide (UO2) having that neutron-capture cross section is low, irradiation stability, fusing point is high, to the anticorrosive of coolant water
Performance is good, has the advantages that good compatibility with cladding materials, is most widely used nuclear fuel material in nuclear industry, but its
Thermal conductivity is minimum in all nuclear fuel materials (metal mold, carbide, nitride).Thermal conductivity is that nuclear fuel is most important
One of thermophysical property, directly determine the performance of nuclear reactor fuel system.Fuel pellet thermal conductivity is lower, reactor
The temperature of fuel assembly is higher during operation, under radiation environment, and thermal stress and the burst size of fission gas are also carried therewith in pellet
Height, so as to cause pellet deformation, cracking, shortens the service life of fuel assembly.In addition, the thermal conductivity of fuel pellet is lower, combustion
The energy storage of material system is higher, and the safety margin of reactor operation will be greatly reduced in this, is particularly occurring coolant loss
During nuclear accident (Loss Of Coolant Accident, LOCA), the energy that fuel system is stored can not be discharged rapidly
It will result directly in fuel system temperature drastically to raise, pellet creep, cave in, reactor core melts down, radioactive substance is exposed, such as cannot
Effectively control will trigger serious nuclear accident.After Fukushima, Japan nuclear accident, people start to recognize traditional uranium dioxide thermal conductivity
The low defect of rate have become influence nuclear power station operation major safety risks (R.O.Meyer, Nucl.Technol., 2006,
155:293).In order to solve this problem, it is necessary to optimize design with structure to existing nuclear fuel composition, improve it in design
Basis accident situation and the security under accident condition beyond design basis, bear so as to mitigate reactor safety system
Load, it is ensured that reactor safety is run.
The content of the invention
The invention aims to solve above-mentioned technical problem, there is provided a kind of metal reinforced uranium dioxide cartridge
The preparation method of block, prepares thermal conductivity and is substantially better than pure UO2And resistance to gentle irradiation stability can be excellent metal reinforced two
Urania fuel ball, improves the level of security of reactor and fuel system.
To achieve the above object, the technical solution adopted by the present invention is as follows：
A kind of preparation method of metal reinforced uranium dioxide fuel ball, comprises the following steps：
(1) powder of uranium dioxide is subjected to the quick pre-burning of low temperature, the quick pre-burning of low temperature by discharge plasma sintering method
Cheng Zhong, is warming up to after 600~800 DEG C with 50~200 DEG C/min heating rate, is incubated 1~10min, is obtained uranium dioxide pre-
Sintering briquette；
(2) the uranium dioxide particle of the mesh of particle diameter 15~100 is obtained after uranium dioxide presintered compact being crushed, sieved, so
Uranium dioxide particulate abrasive nodularization 2~12 hours is obtained into uranium dioxide bead again afterwards；
(3) by uranium dioxide bead and metal dust by volume 1:0.05~0.15 ratio carries out mixing cladding 2~8
Hour, obtain the core-shell structure particles that metal dust is evenly coated in uranium dioxide bead surface；
(4) core-shell structure particles are pressed into density for 5.6~6.8g/cm3Metal reinforced fuel ball biscuit；
(5) by metal reinforced fuel ball biscuit by discharge plasma sintering method in argon gas or argon hydrogen mixture gas
High temperature sintering is carried out under atmosphere, sintering temperature is after 1600~1900 DEG C, is incubated 2~8 hours, and then cooling can be obtained with micro-
The metal reinforced uranium dioxide fuel ball of born of the same parents' structure.
Specifically, in the step (1), the particle diameter of the powder of uranium dioxide is 50nm~200 μm.
Specifically, the uranium dioxide presintered compact density obtained in the step (1) is 5.0~6.5g/cm3。
Specifically, in the step (3), the particle diameter of metal dust is 20nm~50 μm.
In particular, the metal dust is the one or more in molybdenum, chromium, tungsten.
Compared with prior art, the invention has the advantages that：
(1) present invention sinters (Spark Plasma Sintering, SPS) quick pre-burning of low temperature using discharge plasma
Technique can obtain the UO of low-density, high intensity2Presintered compact, good sphericity, density are obtained after broken, sieving, spheroidising
The high UO of low, intensity2Bead, the characteristic can promote metal dust in the cladding of UO2 bead surfaces, obtain covered effect good
Uranium dioxide/metal core-shell structure particles；The core-shell structure particles are shaped with after high temperature sintering, are coated on UO2Particle surface
Metal dust local liquefaction and be interconnected, in UO2The metal micella of similar cell membrane structure is formd around particle；The knot
Structure characteristic can significantly reduce the interface resistance that heat is gone to inside pellet, so that the thermal conductivity of fuel pellet is relative to pure UO2Have
Greatly improve, the metal reinforced uranium dioxide pellet relative to direct mixed sintering is also obviously improved.
(2) present invention low, the shadow that solves wide variety of UO2 fuel balls thermal conductivity in existing commercial nuclear reactor
The problem of reactor operation is safe is rung, the thermal conductivity performance of the metal reinforced uranium dioxide fuel ball prepared is obtained
Significantly improve, while also having Elevated temperature irradiation stability in good heap, the level of security of reactor operation can be made to obtain greatly
Width is improved.
Embodiment
With reference to embodiment, the invention will be further described, and mode of the invention includes but are not limited to following implementation
Example.
Embodiment
The purpose of the present embodiment is to solve wide variety of UO2 fuel balls thermal conductivity in existing commercial nuclear reactor
Rate is low, the problem of influence reactor operation is safe, so that a kind of system of the metal reinforced uranium dioxide fuel ball provided
Preparation Method.The preparation method mainly includes two big steps, and one is to prepare core-shell structure particles, i.e., sintered using discharge plasma
(Spark Plasma Sintering, SPS) technology is to UO2Powder carries out the quick pre-burning of low temperature, and UO is obtained after granulation, nodularization2
Bead, then the mode with metal (one of Mo, Cr, W etc.) micro mist progress physical mixed, UO2 bead tables are coated to by metal fine powder
Face, is made the core-shell structure particles of metallic cover uranium dioxide；Two be to prepare fuel ball, i.e., using being coated on UO2Bead
After metal (one of Mo, Cr, W etc.) powder metallurgy liquefaction on surface, in UO2Formed around bead similar to the micro- of membrane structure
Born of the same parents' structure continuous phase, with UO2Matrix forms special metal reinforced UO2Fuel ball.Its specific step such as following instance
It is shown：
Example 1
A kind of preparation method of metal reinforced uranium dioxide fuel ball, comprises the following steps：
(1) by UO of the particle diameter for 50nm2Powder is fitted into SPS low temperature presintering special graphite moulds, is subsequently placed in SPS sintering
Carry out in the quick pre-burning of low temperature, the quick burn-in process of low temperature, be warming up to 100 DEG C/min heating rate after 650 DEG C in stove, protected
Warm 5min, obtains density for 5.5g/cm3UO2Presintered compact；
(2) by UO2Presintered compact crushed, sieve after obtain the UO of the mesh of particle diameter 302Particle, then again by UO2Particle loads
Nodularization is ground in nodularization equipment 3 hours, obtains the good UO of sphericity2Bead；
(3) by UO2Bead is fitted into mixing coating equipment, and addition particle diameter is 50 μm, volume is UO2The 0.08 of bead volume
Metal molybdenum (Mo) powder again, carries out mixing cladding 4 hours, obtains metal molybdenum powder in UO2The core that bead surface is evenly coated
Shell structure granules；
(4) core-shell structure particles are fitted into powder metallurgy forming mold, are pressed into density for 6.0g/cm3Metal increase
Strong type fuel ball biscuit；
(5) metal reinforced fuel ball biscuit is loaded in atmosphere sintering furnace, existed by discharge plasma sintering method
High temperature sintering is carried out under argon hydrogen gaseous mixture atmosphere, sintering temperature is after 1600 DEG C, is incubated 8 hours, and then cooling can be had
There is the enhanced UO of metal molybdenum of micro-cell structure2Fuel ball.
Example 2
(1) it is 100 μm of UO by particle diameter2Powder is fitted into SPS low temperature presintering special graphite moulds, is subsequently placed in SPS burnings
Carry out in the quick pre-burning of low temperature, the quick burn-in process of low temperature, be warming up to 50 DEG C/min heating rate after 700 DEG C in freezing of a furnace,
1min is incubated, density is obtained for 5.0g/cm3UO2Presintered compact；
(2) by UO2Presintered compact crushed, sieve after obtain the UO of the mesh of particle diameter 152Particle, then again by UO2Particle loads
Nodularization is ground in nodularization equipment 2 hours, obtains the good UO of sphericity2Bead；
(3) by UO2Bead is fitted into mixing coating equipment, and addition particle diameter is that 50nm, volume are UO2The 0.12 of bead volume
Crome metal (Cr) powder again, carries out mixing cladding 2 hours, obtains crome metal powder in UO2The core that bead surface is evenly coated
Shell structure granules；
(4) core-shell structure particles are fitted into powder metallurgy forming mold, are pressed into density for 5.6g/cm3Metal increase
Strong type fuel ball biscuit；
(5) metal reinforced fuel ball biscuit is loaded in atmosphere sintering furnace, existed by discharge plasma sintering method
High temperature sintering is carried out under argon gas atmosphere, sintering temperature is after 1750 DEG C, is incubated 4 hours, and then cooling can be obtained with micella
The enhanced UO of crome metal of structure2Fuel ball.
Example 3
(1) it is 20 μm of UO by particle diameter2Powder is fitted into SPS low temperature presintering special graphite moulds, is subsequently placed in SPS sintering
Carry out in the quick pre-burning of low temperature, the quick burn-in process of low temperature, be warming up to 150 DEG C/min heating rate after 700 DEG C in stove, protected
Warm 5min, obtains density for 6.2g/cm3UO2Presintered compact；
(2) by UO2Presintered compact crushed, sieve after obtain the UO of the mesh of particle diameter 802Particle, then again by UO2Particle loads
Nodularization is ground in nodularization equipment 8 hours, obtains the good UO of sphericity2Bead；
(3) by UO2Bead is fitted into mixing coating equipment, and addition particle diameter is that 20nm, volume are UO2The 0.15 of bead volume
Tungsten (W) powder again, carries out mixing cladding 6 hours, obtains tungsten powder in UO2The core that bead surface is evenly coated
Shell structure granules；
(4) core-shell structure particles are fitted into powder metallurgy forming mold, are pressed into density for 6.8g/cm3Metal increase
Strong type fuel ball biscuit；
(5) metal reinforced fuel ball biscuit is loaded in atmosphere sintering furnace, existed by discharge plasma sintering method
High temperature sintering is carried out under argon hydrogen gaseous mixture atmosphere, sintering temperature is after 1900 DEG C, is incubated 5 hours, and then cooling can be had
There is the enhanced UO of tungsten of micro-cell structure2Fuel ball.
Example 4
(1) it is 100 μm of UO by particle diameter2Powder is fitted into SPS low temperature presintering special graphite moulds, is subsequently placed in SPS burnings
Carry out in the quick pre-burning of low temperature, the quick burn-in process of low temperature, be warming up to 100 DEG C/min heating rate after 600 DEG C in freezing of a furnace,
10min is incubated, density is obtained for 5.8g/cm3UO2Presintered compact；
(2) by UO2Presintered compact crushed, sieve after obtain the UO of the mesh of particle diameter 602Particle, then again by UO2Particle loads
Nodularization is ground in nodularization equipment 6 hours, obtains the good UO of sphericity2Bead；
(3) by UO2Bead is fitted into mixing coating equipment, and addition particle diameter is 20 μm, volume is UO2The 0.05 of bead volume
Metal molybdenum (Mo) powder again, carries out mixing cladding 3 hours, obtains metal molybdenum powder in UO2The core that bead surface is evenly coated
Shell structure granules；
(4) core-shell structure particles are fitted into powder metallurgy forming mold, are pressed into density for 5.8g/cm3Metal increase
Strong type fuel ball biscuit；
(5) metal reinforced fuel ball biscuit is loaded in atmosphere sintering furnace, existed by discharge plasma sintering method
High temperature sintering is carried out under argon gas atmosphere, sintering temperature is after 1800 DEG C, is incubated 2 hours, and then cooling can be obtained with micella
The enhanced UO of metal molybdenum of structure2Fuel ball.
Example 5
(1) it is 200 μm of UO by particle diameter2Powder is fitted into SPS low temperature presintering special graphite moulds, is subsequently placed in SPS burnings
Carry out in the quick pre-burning of low temperature, the quick burn-in process of low temperature, be warming up to 200 DEG C/min heating rate after 800 DEG C in freezing of a furnace,
2min is incubated, density is obtained for 6.5g/cm3UO2Presintered compact；
(2) by UO2Presintered compact crushed, sieve after obtain the UO of the mesh of particle diameter 1002Particle, then again by UO2Particle is filled
Enter and nodularization is ground in nodularization equipment 12 hours, obtain the good UO of sphericity2Bead；
(3) by UO2Bead is fitted into mixing coating equipment, and addition particle diameter is 50 μm, volume is UO2The 0.1 of bead volume
Crome metal (Cr) powder again, carries out mixing cladding 5 hours, obtains crome metal powder in UO2The core that bead surface is evenly coated
Shell structure granules；
(4) core-shell structure particles are fitted into powder metallurgy forming mold, are pressed into density for 6.5g/cm3Metal increase
Strong type fuel ball biscuit；
(5) metal reinforced fuel ball biscuit is loaded in atmosphere sintering furnace, existed by discharge plasma sintering method
High temperature sintering is carried out under argon gas atmosphere, sintering temperature is after 1700 DEG C, is incubated 5 hours, and then cooling can be obtained with micella
The enhanced UO of crome metal of structure2Fuel ball.
By above example it can be found that the present embodiment is using thermal conductivity is high, fusing point is high, neutron absorption cross-section is small, anti-
The metal materials such as the good molybdenum of irradiation behaviour (Mo), chromium (Cr), tungsten (W) strengthen phase and UO as thermal conductivity2Mixed, coated,
Shaping, sintering processes, prepare thermal conductivity and are substantially better than pure UO2, the metal reinforced dioxy that resistance to gentle irradiation stability can be excellent
Change uranium nuclear fuel pellet, can be effectively improved the level of security of reactor and fuel system.
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 (5)
1. a kind of preparation method of metal reinforced uranium dioxide fuel ball, it is characterised in that comprise the following steps：
（1）Powder of uranium dioxide is carried out in the quick pre-burning of low temperature, the quick burn-in process of low temperature by discharge plasma sintering method,
It is warming up to 50 ~ 200 DEG C/min heating rate after 600 ~ 800 DEG C, is incubated 1 ~ 10min, obtains uranium dioxide presintered compact；
（2）The uranium dioxide particle of the mesh of particle diameter 15 ~ 100 is obtained after uranium dioxide presintered compact is crushed, sieved, then again will
Uranium dioxide particulate abrasive nodularization 2 ~ 12 hours, obtains uranium dioxide bead；
（3）By uranium dioxide bead and metal dust by volume 1:0.05 ~ 0.15 ratio carries out mixing cladding 2 ~ 8 hours,
Obtain the core-shell structure particles that metal dust is evenly coated in uranium dioxide bead surface；
（4）Core-shell structure particles are pressed into density for 5.6 ~ 6.8g/cm3Metal reinforced fuel ball biscuit；
（5）By metal reinforced fuel ball biscuit by discharge plasma sintering method under argon gas or argon hydrogen gaseous mixture atmosphere
High temperature sintering is carried out, sintering temperature is after 1600 ~ 1900 DEG C, is incubated 2 ~ 8 hours, and then cooling can be obtained with micro-cell structure
Metal reinforced uranium dioxide fuel ball.
2. a kind of preparation method of metal reinforced uranium dioxide fuel ball according to claim 1, its feature exists
In the step（1）In, the particle diameter of the powder of uranium dioxide is 50nm ~ 200 μm.
3. a kind of preparation method of metal reinforced uranium dioxide fuel ball according to claim 2, its feature exists
In the step（1）In obtained uranium dioxide presintered compact density be 5.0 ~ 6.5g/cm3。
4. a kind of preparation method of metal reinforced uranium dioxide fuel ball according to claim 3, its feature exists
In the step（3）In, the particle diameter of metal dust is 20nm ~ 50 μm.
5. a kind of preparation side of metal reinforced uranium dioxide fuel ball according to claim 1 ~ 4 any one
Method, it is characterised in that the metal dust is the one or more in molybdenum, chromium, tungsten.
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| CN107731318A (en) * | 2017-10-27 | 2018-02-23 | 中国工程物理研究院材料研究所 | A kind of preparation method of monocrystalline uranium dioxide fuel ball |
| CN107871540A (en) * | 2017-10-27 | 2018-04-03 | 中国工程物理研究院材料研究所 | A kind of preparation method of big crystal grain high heat conductance uranium dioxide pellet |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2000007194A1 (en) * | 1998-07-27 | 2000-02-10 | Georgetown University | Preparation of tungsten bronzes for nuclear waste storage forms and electronic materials |
| CN1544392A (en) * | 2003-11-20 | 2004-11-10 | 西安中天科技有限责任公司 | Low-temperature sintering lead-containing dielectric ceramic and its production method |
| CN103299375A (en) * | 2010-09-27 | 2013-09-11 | 普渡研究基金会 | Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith |
| CN105642907A (en) * | 2016-01-29 | 2016-06-08 | 中国核动力研究设计院 | UO2-W metal ceramic ball preparation method |
| CN105706177A (en) * | 2013-11-26 | 2016-06-22 | 阿科姆工程合资(控股)公司 | Nuclear fuel pellet having enhanced thermal conductivity, and preparation method thereof |
-
2017
- 2017-07-03 CN CN201710533031.7A patent/CN107256726B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2000007194A1 (en) * | 1998-07-27 | 2000-02-10 | Georgetown University | Preparation of tungsten bronzes for nuclear waste storage forms and electronic materials |
| CN1544392A (en) * | 2003-11-20 | 2004-11-10 | 西安中天科技有限责任公司 | Low-temperature sintering lead-containing dielectric ceramic and its production method |
| CN103299375A (en) * | 2010-09-27 | 2013-09-11 | 普渡研究基金会 | Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith |
| CN105706177A (en) * | 2013-11-26 | 2016-06-22 | 阿科姆工程合资(控股)公司 | Nuclear fuel pellet having enhanced thermal conductivity, and preparation method thereof |
| CN105642907A (en) * | 2016-01-29 | 2016-06-08 | 中国核动力研究设计院 | UO2-W metal ceramic ball preparation method |
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Inventor after: Yang Zhenliang Inventor after: Liu Tong Inventor after: Li Bingqing Inventor after: Huang Huawei Inventor after: Gao Rui Inventor after: Sun Maozhou Inventor after: Zhang Pengcheng Inventor after: Jia Jianping Inventor after: Yang Zhenliang, Liu Tong, Li Bingqing, Huang Huawei, Gao Ruisun, Maozhou, Zhang Pengcheng, Jia Jianping, Ma Zhaodandan Inventor before: Yang Zhenliang Inventor before: Liu Tong Inventor before: Li Bingqing Inventor before: Huang Huawei Inventor before: Gao Rui Inventor before: Sun Maozhou Inventor before: Jia Jianping Inventor before: Yang Zhenliang, Liu Tong, Li Bingqing, Huang Huawei, Gao Ruisun, Jia Jianping, Ma Zhaodandan, Maozhou |